ORAU TEAM

Dose Reconstruction

Project for NIOSH

Oak Ridge Associated Universities I Dade Moeller & Associates I MJW Corporation

Page 1 of 56

Document Title:

Hanford Site – Occupational Environmental Dose

Document Number: ORAUT-TKBS-0006-4

Revision: 02

Effective Date: 06/05/2007

Type of Document TBD

Supersedes: Revision 01

Subject Expert(s): N/A

Site Expert(s): Bruce A. Napier

Approval: Signature on File Approval Date: 05/30/2007

Edward D. Scalsky, Document Owner

Concurrence: Signature on File Concurrence Date: 05/29/2007

John M. Byrne, Task 3 Manager

Concurrence: Signature on File Concurrence Date: 06/01/2007

Edward F. Maher, Task 5 Manager

Concurrence: Signature on File Concurrence Date: 05/31/2007

Kate Kimpan, Project Director

Approval: Brant A. Ulsh Signature on File for Approval Date: 06/05/2007

James W. Neton, Associate Director for Science

 New Total Rewrite Revision Page Change

FOR DOCUMENTS MARKED AS A TOTAL REWRITE, REVISION, OR PAGE CHANGE, REPLACE THE PRIOR 

REVISION AND DISCARD / DESTROY ALL COPIES OF THE PRIOR REVISION.
Document No. ORAUT-TKBS-0006-4 Revision No. 02 Effective Date: 06/05/2007 Page 2 of 56

PUBLICATION RECORD

EFFECTIVE 

DATE

REVISION 

NUMBER DESCRIPTION

10/15/2003 00 New document to establish Occupational Environmental Dose 

Section 4. First approved issue. Initiated by Edward D. Scalsky.

12/20/2006 01 Approved revision as a result of the biennial document review. 

Revises Section 4.3.3 to respond to SC&A comments. Table 4-3 

was revised to include more absorption types, in accordance with 

ICRP 68, and type S Sr was removed. Tables A-13 through A-21 

were removed and replaced by revised Tables A-11-13 that provides 

only one air concentration per radionuclide per year. Incorporates 

internal and NIOSH formal review comments. Constitutes a total 

rewrite of document. This revision results in an increase in assigned 

dose and a PER is required. Training required: As determined by 

the Task Manager. Initiated by Edward D. Scalsky.

06/05/2007 02 Approved revision initiated to include Attributions and Annotations. 

No further changes occurred as a result of formal internal review.

This revision results in no change to the assigned dose and no PER 

is required. Training required: As determined by the Task Manager. 

Initiated by Edward D. Scalsky.
Document No. ORAUT-TKBS-0006-4 Revision No. 02 Effective Date: 06/05/2007 Page 3 of 56

TABLE OF CONTENTS

SECTION TITLE

Acronyms and Abbreviations ...............................................................................................................

PAGE

6

4.1 Introduction ..............................................................................................................................7

4.1.1 Purpose........................................................................................................................8

4.1.2 Scope...........................................................................................................................8

4.2 Doses from Onsite Atmospheric Radionuclide Concentrations................................................. 8

4.2.1 Onsite Releases to Air..................................................................................................9

4.2.1.1 Routine Releases from T and B Plants......................................................... 11

4.2.1.2 Routine Releases of Plutonium from Z Plant................................................ 17

4.2.1.3 Routine Releases of Iodine from the Chemical Separations Plants .............. 17

4.2.1.4 Nonroutine Releases from the REDOX Plant ............................................... 18

4.2.1.5 Releases of Tritium from 108-B.................................................................... 18

4.2.2 Environmental Air Monitoring......................................................................................19

4.2.3 Intake of Airborne Radionuclides ................................................................................19

4.3 External Dose ........................................................................................................................22

4.3.1 Ambient Radiation ......................................................................................................22

4.3.2 Releases of Noble Gases ...........................................................................................24

4.3.2.1 Xenon .......................................................................................................... 24

4.3.2.2 Argon Releases from the Production Reactors............................................. 27

4.3.3 Skin Deposition of Airborne Particulate Emissions......................................................27

4.4 Attributions and Annotations .................................................................................................. 31

References ........................................................................................................................................34

ATTACHMENT A...............................................................................................................................39
Document No. ORAUT-TKBS-0006-4 Revision No. 02 Effective Date: 06/05/2007 Page 4 of 56

LIST OF TABLES

TABLE TITLE

4-1 Facility operation dates .......................................................................................................

PAGE

10

4-2 Estimated release rates from Hanford reactors with air pathway screening 

factors for 41Ar, 3

H, and 14C ................................................................................................. 11

4-3 Assumed absorption types for each radionuclide ................................................................ 11

4-4 Physical, chemical, and radiological properties of radioactive particles 

released from 1945 to 1956 ................................................................................................ 13

4-5 Annual amount of tritium released from 108-B..................................................................... 19

4-6 Selected receptor locations with identifying computational nodes ....................................... 21

4-7 Maximum intakes by radionuclide........................................................................................ 22

4-8 External gamma radiation ................................................................................................... 25

4-9 Distributions of monthly release estimates for 41Ar from reactors and Areas ....................... 27

4-10 Concentrations of 41Ar measured in effluent flow rates for production reactor 

stacks..................................................................................................................................27

4-11 Probability of interaction of an individual with at least one T- or B-Plant 

particle by receptor location and by month for a 10% use factor.......................................... 29

4-12 Probability of interaction of an individual with at least one REDOX particle 

by receptor location and by month for a 10% use factor...................................................... 30

4-13 Dose coefficients for radionuclides contained in Hanford active particles ............................ 30

A-1 Source term data for 131I releases........................................................................................ 40

A-2 Source term data for 41Ar releases ...................................................................................... 41

A-3 Source term data for 144Ce/144Pr particulate releases .......................................................... 43

A-4 Source term data for 137Cs/137mBa particulate releases ........................................................ 44

A-5 Source term data for 239Pu particulate releases................................................................... 45

A-6 Source term data for 103Ru/103mRh particulate releases........................................................ 46

A-7 Source term data for 106Ru/106Rh particulate releases ......................................................... 47

A-8 Source term data for 90Sr/90Y particulate releases ............................................................... 48

A-9 Source term data for 95Zr/95Nb particulate releases ............................................................. 49

A-10 Atmospheric dispersion factors ........................................................................................... 50

A-11 Ar-41 submersion gamma dose (Sv) and skin dose (Sv)..................................................... 53

A-12 Intakes of particulate radionuclides ..................................................................................... 54

A-13 Intakes from 3H from 108-B................................................................................................. 56
Document No. ORAUT-TKBS-0006-4 Revision No. 02 Effective Date: 06/05/2007 Page 5 of 56

LIST OF FIGURES

FIGURE TITLE

4-1 Locations of potential exposure for intakes and exposures ...................................................

PAGE

9

4-2 Average fuel cooling times before processing ..................................................................... 10

4-3 Estimated distributions of physical and aerodynamic diameters for large, 

“active particles” with estimated distributions for particle surface area and 

activity.................................................................................................................................12

4-4 Estimated releases of 144Ce from T Plant ............................................................................ 16

4-5 Estimated releases of 131I from T Plant................................................................................ 16

4-6 Estimated releases of 239Pu from Z Plant............................................................................. 17

4-7 Estimated releases of 106Ru from REDOX Plant.................................................................. 18

4-8 Radiation levels at two locations, 1945 to 1948................................................................... 23

4-9 Exposure rates measured near the REDOX Plant and at four military 

installations .........................................................................................................................23

4-10 Time trends in annual 131I and 106Ru releases to air with net exposure rates 

between the 200 Areas (Building 622) and at the REDOX plant perimeter.......................... 24
Document No. ORAUT-TKBS-0006-4 Revision No. 02 Effective Date: 06/05/2007 Page 6 of 56

ACRONYMS AND ABBREVIATIONS

BMIPND Battelle Memorial Institute – Pacific Northwest Division

Bq becquerel

Ci curie

cm centimeter

d day

DOE U.S. Department of Energy 

EEOICPA Energy Employees Occupational Illness Compensation Program Act of 2000

ft foot

GM geometric mean

GSD geometric standard deviation

in. inch

km kilometer

m meter

MeV megaelectron-volt, 1 million electron-volts

mg milligram

mo month

mrad millirad

mrep millirep

nCi nanocurie

nGy nanogray

NIOSH National Institute for Occupational Safety and Health

ORAU Oak Ridge Associated Universities

pCi picocurie

POC probability of causation

PUREX plutonium–uranium extraction

REDOX reduction oxidation

s second

Sv sievert

TBD technical basis document

TBq terabecquerel

U.S.C. United States Code

yr year

μCi microcurie

μm micrometer

§ section or sections
Document No. ORAUT-TKBS-0006-4 Revision No. 02 Effective Date: 06/05/2007 Page 7 of 56

4.1 INTRODUCTION

Technical basis documents and site profile documents are not official determinations made by the 

National Institute for Occupational Safety and Health (NIOSH) but are rather general working 

documents that provide historic background information and guidance to assist in the preparation of 

dose reconstructions at particular sites or categories of sites. They will be revised in the event 

additional relevant information is obtained about the affected site(s). These documents may be used 

to assist NIOSH staff in the completion of the individual work required for each dose reconstruction.

In this document the word “facility” is used as a general term for an area, building, or group of 

buildings that served a specific purpose at a site. It does not necessarily connote an “atomic weapons 

employer facility” or a “Department of Energy [DOE] facility” as defined in the Energy Employees 

Occupational Illness Compensation Program Act [EEOICPA; 42 U.S.C. § 7384l(5) and (12)]. 

EEOICPA defines a DOE facility as “any building, structure, or premise, including the grounds upon 

which such building, structure, or premise is located ... in which operations are, or have been, 

conducted by, or on behalf of, the Department of Energy (except for buildings, structures, premises, 

grounds, or operations ... pertaining to the Naval Nuclear Propulsion Program)” [42 U.S.C. § 

7384l(12)]. Accordingly, except for the exclusion for the Naval Nuclear Propulsion Program noted 

above, any facility that performs or performed DOE operations of any nature whatsoever is a DOE 

facility encompassed by EEOICPA.

For employees of DOE or its contractors with cancer, the DOE facility definition only determines 

eligibility for a dose reconstruction, which is a prerequisite to a compensation decision (except for 

members of the Special Exposure Cohort). The compensation decision for cancer claimants is based 

on a section of the statute entitled “Exposure in the Performance of Duty.” That provision [42 U.S.C. § 

7384n(b)] says that an individual with cancer “shall be determined to have sustained that cancer in the 

performance of duty for purposes of the compensation program if, and only if, the cancer ... was at 

least as likely as not related to employment at the facility [where the employee worked], as 

determined in accordance with the POC [probability of causation1

As noted above, the statute includes a definition of a DOE facility that excludes “buildings, structures, 

premises, grounds, or operations covered by Executive Order No. 12344, dated February 1, 1982 (42 

U.S.C. 7158 note), pertaining to the Naval Nuclear Propulsion Program” [42 U.S.C. § 7384l(12)]. 

While this definition contains an exclusion with respect to the Naval Nuclear Propulsion Program, the 

section of EEOICPA that deals with the compensation decision for covered employees with cancer 

[i.e., 42 U.S.C. § 7384n(b), entitled “Exposure in the Performance of Duty”] does not contain such an 

exclusion. Therefore, the statute requires NIOSH to include all occupationally derived radiation 

exposures at covered facilities in its dose reconstructions for employees at DOE facilities, including 

radiation exposures related to the Naval Nuclear Propulsion Program. As a result, all internal and 

external dosimetry monitoring results are considered valid for use in dose reconstruction. No efforts 

are made to determine the eligibility of any fraction of total measured exposure for inclusion in dose 

reconstruction. NIOSH, however, does not consider the following exposures to be occupationally 

derived:

] guidelines established under 

subsection (c) ...” [42 U.S.C. § 7384n(b)]. Neither the statute nor the probability of causation 

guidelines (nor the dose reconstruction regulation) define “performance of duty” for DOE employees 

with a covered cancer or restrict the “duty” to nuclear weapons work.

• Radiation from naturally occurring radon present in conventional structures 

 

1 The U.S. Department of Labor is ultimately responsible under the EEOICPA for determining the probability of causation 

(POC). 
Document No. ORAUT-TKBS-0006-4 Revision No. 02 Effective Date: 06/05/2007 Page 8 of 56

• Radiation from diagnostic X-rays received in the treatment of work-related injuries 

4.1.1

This TBD provides the rationale, historical background, and data for the reconstruction of occupational 

environmental doses for unmonitored personnel at the Hanford Site. The occupational environmental 

dose is the dose received by individuals while outside of operational facilities on the site such as 

process buildings, chemical separations plants, reactors, or other structures. Internal dose from the 

inhalation of radioactive materials may be determined from radionuclide air concentrations. External 

dose from radioactive materials outside the body may be determined from immersion in a cloud of 

inert gases, from deposition of particles on the skin, or from adjacent operational facilities. 

Purpose

4.1.2

This TBD provides information on the routine releases from the various Hanford facilities and the 

doses received by personnel as a result of these releases.

Scope

The four chemical separations plants, T Plant, B Plant, REDOX Plant, and PUREX Plant, along with 

the plutonium-handling Z Plant, are shown in Figure 4-1 and are the most important release points at 

Hanford. Section 4.3.2 shows that 41Ar from the reactors was also an important source of worker 

exposure. For individuals working outside process buildings and facilities at Hanford, pathways of 

concern are [1]: 

• The inhalation of radionuclides in the air. 

• Direct external radiation from plumes. 

• Physical contact with particulate radionuclides incident on the skin. 

Construction workers, contractors, security guards, environmental monitoring personnel, and 

personnel involved with outdoor work duties would be the personnel likely to receive occupational 

environmental doses [2]. 

Gerber (1992) shows the location of the Hanford Camp, the Columbia Camp, and other locations 

where individuals worked and lived. For example, up to 40,000 individuals, mainly construction 

workers, resided at Hanford Camp until it closed in February 1945. Gerber (1993) provides details on 

the buildings and facilities. Figure 4-1 shows many of these locations, which were selected as 

locations where annual intakes of radionuclides in the air were determined.

Attributions and annotations, indicated by bracketed callouts and used to identify the source, 

justification, or clarification of the associated information, are presented in Section 4.4. 

4.2 DOSES FROM ONSITE ATMOSPHERIC RADIONUCLIDE CONCENTRATIONS

In 1943 the Hanford Site was selected as the location to produce plutonium for the U.S. atomic 

weapons program (Groves 1962). Nine reactors, four chemical separations plants, and a plutoniumhandling plant became operational at the site in the following years (Ballinger and Hall 1991; Gydesen 

1992; Till et al. 2002). Table 4-1 lists the dates of operation of these facilities.

The plutonium produced in the reactor fuel elements was extracted from the irradiated fuel in the 

chemical separations plants (T, B, REDOX, and PUREX) and converted to metallic plutonium in the 

Z plant. Throughout operations of the reactors, chemical separations plants, and Z Plant, a portion of 
Document No. ORAUT-TKBS-0006-4 Revision No. 02 Effective Date: 06/05/2007 Page 9 of 56

Figure 4-1. Locations of potential exposure for intakes and exposures. [3]

the radionuclides being processed was released into the atmosphere and transported primarily 

downwind to the northeast (Farris et al. 1994).

4.2.1

Figure 4-2 shows the fuel element cooling time, which is the elapsed time between discharge of the 

fuel elements from the reactors and the start of fuel processing in the chemical plants. Between 1944 

and 1945 the fuel element cooling time was approximately 40 d. By 1947 the cooling time was 

Onsite Releases to Air
Document No. ORAUT-TKBS-0006-4 Revision No. 02 Effective Date: 06/05/2007 Page 10 of 56

Table 4-1. Facility operation dates. 

Facility Dates of operation

Reactors

100-B 1944–1968

100-D 1944–1967

100-F 1945–1965

100H 1949–1965

100-DR 1950–1964

100-C 1952–1969

100-KE 1955–1971

100-KW 1955–1970

100-N 1963–1987

Chemical separations plants

T 1944–1956

B 1945–1952

REDOX 1952–1966

PUREX 1956–1990

Pu-handling plant

Z 1949–1976

extended to approximately 90 d. The shorter cooling time resulted in the releases of larger quantities 

of volatile, short-lived radionuclides in comparison to later years. For example, in 1945 up to 90,000 

Ci of 131I were released each month compared to 10,000 Ci/mo after 1946. Because there was no 

filtration to limit release of the volatile radionuclides in the earliest years, the releases to the 

atmosphere in 1945 were the largest at any time at Hanford (Till et al. 2002). 

0

20

40

60

80

100

Average cooling time (days)

Date

Dec

1944

Nov

1945

Nov

1946

Nov

1947

Figure 4-2. Average fuel cooling times before processing. 

Heeb (1994) lists the releases of 41Ar, 14C, and 3

H from the reactors based on historical 

measurements. Screening studies eliminated from dose consideration 3

H and 14C releases to the 

atmosphere from the reactors based on the product of the amount released and the dose conversion 

factors shown in Table 4-2. The estimated dose contribution of 41Ar was 10,000 times greater than 
Document No. ORAUT-TKBS-0006-4 Revision No. 02 Effective Date: 06/05/2007 Page 11 of 56

that of 3H and 3,000 times greater than that of 14C. However, due to the large 3H release from the 

108-B facility, the dose from 3

H was assessed. Section 4.2.1.5 contains more information on releases 

of tritium for 108-B, and Section 4.3.2 contains additional information on 41Ar.

Table 4-2. Estimated release rates from Hanford reactors with air pathway 

screening factors for 41Ar, 3

H, and 14C. 

Radionuclide

Estimated release 

from all reactors 

(Bq/d)a

Screening factor for inhalation 

and direct radiation exposure 

(Sv per Bq/m3)

b

Ar-41 5.5E+13 1.5E-06

H-3 5.2E+10 1.4E-07

C-14 3.7E+09 4.5E-06

a. Release estimates from Heeb (1994). 

b. Screening factors from Appendix B of NCRP (1996). 

Similar screening of the radionuclides released demonstrated that the dose from the radionuclides 

listed in Table 4-3 should be considered (Till et al. 2002). The table lists the assumed absorption 

types for each radionuclide. Radionuclides listed in pairs are parents with associated short-lived 

progeny. These are assumed to be in equilibrium in the environment. Source terms are release rates 

of radioactive materials at specific locations. Tables A-1 to A-9 in ATTACHMENT A list the source 

terms for the reactors, chemical separations plants, and the plutonium-handling plant.

Table 4-3. Assumed absorption typesa for each radionuclide [4]. 

Radionuclide Absorption type

Ar-41 Not applicable

H-3 Water

Gas (HT or T2) submersion

I-131 Class SR-1, type F or

vapor

Ce-144/Pr-144 M for all compounds except oxides, hydroxides, and fluorides

S for oxides

Cs-137 F for all compounds

Pu-239 M for unspecified compounds or

S for insoluble oxides

Ru-103/Rh-103 F for unspecified compounds or

S for oxides and hydroxides

Ru-106/Rh-106 F for unspecified compounds or

S for oxides and hydroxides

Sr-90/Y-90 F for all compounds

Zr-95/Nb-95 F for all compounds except

M for oxides, hydroxides, halides, and nitrates

S for carbides

a. F = fast; M = moderate; S = slow. 

4.2.1.1 Routine Releases from T and B Plants

Stack releases to the environment under normal operating conditions at the chemical separations 

plants were proportional to the rates at which the material entered as irradiated fuel from the reactors. 

The most likely source of these releases was iron-oxide particulates from corroding ductwork in the 

ventilation systems of the T and B Plants. Analysis of the particles indicated that the radionuclides 

were deposited on the blowers and other iron surfaces and were released into the ventilation air 

stream as the iron parts corroded. Figure 4-3 shows the estimated distributions of physical, 

aerodynamic, and radiological properties of the released particles. Other physical characteristics of 
Document No. ORAUT-TKBS-0006-4 Revision No. 02 Effective Date: 06/05/2007 Page 12 of 56

the particles and their distributions are reported in Michelson (1947), Parker (1948a), Gross (1948), 

and Thorburn (1948) (see Table 4-4). 

10

100

1000

10000

.1 1 5 10 20 30 50 70 80 90 95 99 99.9

Percentile

Diameter (μm)

Particle Activity (μCi)

10

1

0.1

0.01

Activity

Surface

Area

Physical

Aerodynamic

Figure 4-3. Estimated distributions of physical and aerodynamic

diameters for large, ”active particles” with estimated distributions 

for particle surface area and activity (Till et al. 2002).

For routine releases from T and B Plants, the estimated monthly release is the product of the following 

factors [5]: 

• The monthly processing rates for each radionuclide compiled by Heeb (1994), which are the 

rates at which the radionuclide enters the separation plants as irradiated fuel from the 

reactors. The processing rates were estimated by Till et al. (2002) for 137Cs and by Heeb 

(1994) for 90Sr, 103Ru, 106Ru, 131I, 144Ce, and 239Pu. 

• The release fraction, which is the ratio of the rate that the radionuclide was released to the 

processing rate of that radionuclide. 

• The effluent treatment modifier, which accounted for increased release rates in the early years 

of operation of T and B Plant when there were no scrubbers or filters on the effluents. 

• Uncertainty factors related to processing rates and the amount of radioactive decay that 

occurred between fuel irradiation and fuel processing. 

Figures 4-4 and 4-5 illustrate the releases of 144Ce and 131I from T Plant. Effluents from B Plant were 

similar to those from T Plant but were higher due to difficulties encountered with the effluent filtration

and scrubber system [6].
Document No. ORAUT-TKB

S-0006-4 Revision No. 0

2 Effective Date:

06/05/2007 Page 13 of 45

Table 4-4. Physical, chemical, and radiological properties of radioactive particles released from 1945 to 1956. Interval Source 

report Location of sample Physical characteristics

Chemical 

Beginning Ending characteristics Radiological characteristics

May 7, 1945 Healy 1945 Stack samples taken 

from the T Plant.

0.6–0.8 MeV beta presumably from 

iodine; also 1.5–2.0 MeV betas.

1945 1947 Healy 1948 Vegetation, processing 

plant effluent air, and 

ambient air.

Total beta 7 nCi/filter.

April 1947 Stainken 1948 Outside near T Plant 

fence.

Presence of singular large particles 

not indicated.

Mostly Ce and decay product Pr.

April 1947 Roberts 1958 Outside in 200 Areas. Effective half-life of about 300 d. 

Principal contaminants were (in order): 

Ce, Y, Sr, Ru, Cs.

Fall 1947 Michelson 

1947

Outside ground near T, 

B Plants. 

Can be mechanically separated from 

dirt.

Total beta activity ranging from 0.5 μCi 

to 1 μCi. Most of the beta activity was 

Ce; most alpha was Pu (range 0.07–

1.7 nCi).

Fall 1947 Parker 1948b Outside ground near T, 

B Plants. 

Color reddish brown; carrier particles 

>100 μm, range 20 to 1500 μm linear 

dimensions; small particles, mists, 

and droplets emitted since 

operations began. 

Contain iron oxides; 

can be separated with 

magnets.

Alpha activity mostly Pu, 1/20 as much 

U. Beta activity correlated with surface 

area of particle; mostly Ce (and 

daughter Pr-144), Y, Sr, Ru, and Cs.

April 1947 Parker 1947 Outside ground near T, 

B Plants. 

Mass of 0.1 to 1 mg; brown color 

(different from soil).

0.1 μCi to 1 μCi. T Plant particles 60–

90% Ce and up to 15%Y. B Plant 30–

55% Ce, 7–20% Sr, and 30–45% Y.

April 1947 April 1948 Parker 1948 Outside ground near T, 

B Plants. 

Physical sizes of 153 large particles 

ranged from 40 μm to >1 mm. 

Median 300 μm. No reliable data on 

very small particles.

Essentially all 

particles contain 

enough iron to be 

separated 

magnetically. 

0.0001 to 3 μCi. 30–50% Ce; 10–50% 

Y; 10–20% Sr.

~March 1948 Gross 1948 Processing plant 

effluent.

Some are <1 μm.

Spring 1948 Adley 1948 Processing plant 

effluent.

Mists mean size <5 μm; magnetic 

specks, density of iron.

Spring 1948 Thorburn 

1948

Ground and roofs 

surrounding processing 

plants.

Usually less than 500 μm; range 20–

1,500 μm.

High in iron; low 

carbon and calcium.

2.5 pCi to 3.2 μCi beta/particle. Max. 

beta energy 3.0 MeV. 

Spring 1948 Thorburn 

1948

Processing plant 

effluent.

Beta mostly Ce; alpha mostly Pu.

~April 1948 Gregg 1948 Outside ground. 10–1,000 μm. Associated with rust. Max 3 μCi beta/particle.

April 1948 April 1948 Singlevich 

1949

Particles collected by 

air samplers.

1–10 pCi fission products/particle.

April 1948 April 1948 Singlevich 

1949

Stacks of 314 Building, 

the Melt Plant, in 300 

Area.

Mostly uranium.

1950 Delong 1950 Ventilation air of the B 

Plant before sand filter.

100% of alpha was Pu; most of beta 

was Ce, rare earths, Ru, Zr, Y, and Sr.

April 3, 1952 Parker 1954 On survey meter inside 

car with window open.

Particle read 40 rad/hr.
Document No. ORAUT-TKB

S-0006-4 Revision No. 0

2 Effective Date:

06/05/2007 Page 14 of 45

Interval Source 

report Location of sample Physical characteristics

Chemical 

Beginning Ending characteristics Radiological characteristics

April 29, 1952 Parker 1954 Eastern and northern 

sections of the REDOX 

area. 

From 100 counts/minute at 1 in. to 

800 mrad/hr at surface; gross beta 

activity ranged up to 0.1 μCi/sample.

April 1952 June 1952 Paas 1952 Particles emitted from 

REDOX Plant (second, 

third, and fourth 

episodic releases on 

April 3, April 29, and 

June 24). 

Ranged from microscopic translucent 

hydroscopic crystals adhering to the 

soil sand, to visible chalky particles 

varying in shape and size—a few 

with diameter ~0.5 in. Larger visible 

particles easily fractured, apparently 

a conglomerate of microscopic 

crystals. 

Chemically, the 

composition of the 

inactive material was 

mainly ammonium 

nitrate with a small 

amount of occluded 

dust particles.

90 to 98% of the total beta activity was 

Ru; I-131 in particulate contamination 

ranged from 1–5%. Beta particle 

activity varied in direct relationship with 

size.

June 24, 1952 Ebright 1954 Outside: flakes from 

fourth episodic release 

from REDOX. 

1/64–1/32-in. thick and up to several 

inches in diameter. Large flaky 

radioactive particles found near the 

eastern REDOX exclusion area 

rapidly disappeared, though activity 

spots were detectable with survey 

instruments. Flakes fragile and 

hydroscopic.

Carrier crystal was 

predominately 

ammonium nitrate. 

Mostly ruthenium.

March 12, 1953 Paas 1953a Ambient air near 

REDOX. 

36% of beta activity was Ru, 43% rare 

earths and Y.

Spring 1953 Adley et al. 

1953

Base (inside) of the 

REDOX stack. 

Median particle size about 0.2 μm 

with GSD of 1.6 during one sample 

and 2.5 during another. 

Activity median particle size was 

0.6 μm. 

August 7, 

1953

August 14, 

1953

Donelson 

1953, Ebright 

1954

Outside ground 

southeasterly direction 

from the REDOX stack. 

Up to 5 in. (13 cm); average 0.5 in. 

(1.3 cm); up to 0.5 to 0.75 in. thick.

Carrier crystals were 

ammonium nitrate. 

Max 15 rep/hr; average 300–500 

mrep/hr surface. 70% Ru, 25% rare 

earths and Y, and trace amounts of Sr, 

Ba, and Zr. 

December 

1953

Adley et al. 

1954

Air entering sand filter 

of REDOX. 

Two cascade impactor sample 

results geometric mean of 0.3 μm 

(GSD 2.8) and 0.5 μm (GSD 3.2); 

ave. 5.3E08 particles/cm3.

December 

1953

Adley et al. 

1954

Air at 10-ft level inside 

REDOX stack. 

Four cascade impactor sample 

results ranged from geometric 

median size 0.3 μm (GSD 2.0) to 0.4 

μm (GSD 3.8); ave. 2.4E08 

particles/cm3.

August 9, 

1954

May 18, 1954 Paas 1954 Air entering REDOX 

Plant sand filter. 

92% of total beta activity was Ru in 

March; in May, 24% was Ru, 28% rare 

earths, 14% Zr, and 25% Nb.

Parker 1954 General review: input 

side of process sand 

filter. 

Less Ru (80%) and more of the rare 

earths (10–15%) and Sr (1–2%), 

compared to particles emitted to the 

environment.
Document No. ORAUT-TKB

S-0006-4 Revision No. 0

2 Effective Date:

06/05/2007 Page 15 of 45

Interval

Source 

report Location of sample Physical characteristics

Chemical 

characteristics Radiological characteristics

1952 1954 Parker 1954 General review: 

REDOX releases to 

environment. 

Primary particles about 2 μm; large 

secondary particles typically 100 μm.

Carrier base is an 

aggregate of 

ammonium nitrate, 

sometimes sand. 

Inhalable particles 

were between 40–

80% soluble after 36 

hr in simulated lung 

fluid. Large particles 

were 3– 70% soluble 

after 48 hr in 

simulated gastric 

juice.

Primary particles up to 5 nCi/particle, 

dose rate of 0.5 mrad/hr; secondary 

particles dose rates up to 20 rad/hr and 

200 μCi/particle. Ru and Rh activity 

98% of the total, with Sr-89 and Sr-90 

<0.3%; rare earths plus Y <1.0%; and 

Zr-95 <0.5%. 

June 1954 Ebright 1954 Outside ground in 200 

Areas. 

No well-defined relationship between 

particle size and dose rate. Particles 

of several thousand square μm were 

observed. Easily fractured.

Ammonium nitrate 

present.

90% of beta activity was Ru; activity 

ratio 103:106 was 0.6 to 1.4; one 

particle with dose rate of 1.2 rad/hr 

contained 6.3 μCi; another reading 

120 mrad/hr had 0.49 μCi; average 

dose rate/μCi was about 200 mrad/hr.

November 7, 

1954

Regional 

Radiation 

Measurement 

Unit 1955

Five particles emitted 

from REDOX stack. 

Four of the particles were 

agglomerates of smaller white 

crystals with yellow discoloration on 

some surfaces. One particle was 

bright yellow without the crystalline 

appearance.

Ammonium nitrate 

and iron were found 

in four particles. The 

bright yellow particle 

was mostly calcium 

and iron.

95% of the beta activity was from 

Ru/Rh isotopes with the ratio of activity 

of 103Ru to 106Ru being less than 0.05. 

Also Sr, rare earths, Zr, Pu.

October 1954 December 

1954

Pilcher et al. 

1954

Ground surfaces 

around REDOX.

Maximum dimensions ranging from a 

few μm to ~1,000 μm.

Nearly all beta was Ru/Rh; Ru-103:Ru106 ratio less than 1.

December 

1954

Healy 1955 Ground surfaces 

around REDOX. 

Relative to a unit length, the average 

width was 0.75 +/ 0.14 and the 

depth was 0.39 +/ 0.18. The 

density is believed to be about 1.5.

May 29, 1956 June 4, 1956 Anderson and 

Soldat 1956

Outside of U Plant in 

200-West Area. 

Large paint flakes up to 8 in. long,

peeled off duct work between sand 

filter and U Plant stack.

Associated with 

painted stack liner.

Alpha and beta.

Note: The blanks in the interval columns in the table indicate the release happened on the date given in the column under ending. 

The blanks in the characteristic column indicate the specific characteristics are not applicable for the stated release.
Document No. ORAUT-TKBS-0006-4 Revision No. 02 Effective Date: 06/05/2007 Page 16 of 56

10-1

100

101

102

103

104

95th %-ile

GM

Estimated monthly releases (GBq) of 144Ce from T Plant

Year

1945 1947 1949 1951 1953 1955

Estimated

release (Ci)

270

27

2.7

0.27

0.027

Figure 4-4. Estimated releases of 144Ce from T Plant (Till et al. 

2002).

101

102

103

104

105

106

107

Estimated median monthly release (GBq)

Year

1945 1947 1949 1951 1953 1955

Estimated

release (Ci)

270

2700

27000

27

2.7

0.27

Figure 4-5. Estimated releases of 131I from T Plant. Heeb 

(1994) and Napier (2002) provided estimates (Till et al. 2002). 
Document No. ORAUT-TKBS-0006-4 Revision No. 02 Effective Date: 06/05/2007 Page 17 of 56

4.2.1.2 Routine Releases of Plutonium from Z Plant

Z plant was not one of the chemical separations plants but was located in the 200-W area of Hanford. 

Z plant produced and fabricated metallic plutonium from plutonium nitrate that came from the 

chemical separations plants. Plutonium-239 was released as small particles of usually less than 

1 μm. Figure 4-6 shows the estimated annual releases of 239Pu from Z Plant as median estimates and 

the 95th percentiles of the distribution (Till et al. 2002). 

101

102

103

104

GM

95th %-ile

Year

1949 1951 1953 1955 1957 1959 1961

Estimated monthly release (MBq)

Estimated

release (mCi)

0.27

2.7

27

Figure 4-6. Estimated releases of 239Pu from Z Plant (Till et al. 

2002).

4.2.1.3 Routine Releases of Iodine from the Chemical Separations Plants

Iodine-131 was released from the four chemical separations plants (T, B, REDOX, and PUREX) from 

1946 until 1962. Screening calculations indicated that 131I was the most important radionuclide 

conveying dose to persons on the site (Till et al. 2002). Heeb (1994), Warren (1961), Junkins et al. 

(1960), and Foster and Nelson (1961) reported estimates of the 131I releases. The estimates were 

complicated by different reported fuel element cooling times for the same fuel elements, unusual 

releases not included in the release estimates such as a boil-over and a fire in a dissolver, the 

presence of organic halides that were not included in the estimates, and unaccounted for plateout of 

elemental iodine in the sampling systems. Figure 4-5 shows the estimates of 131I releases for T Plant. 

The estimates were compiled by Till et al. (2002) based on the amount of iodine in the fuel elements 

sent to the dissolvers of the chemical separations plants (Heeb 1994) and the stack monitoring data 

and environmental measurements (Napier 2002). The absorption type for all compounds of iodine is 

F, and it is assumed to be a class SR-1 vapor for internal dose calculations.
Document No. ORAUT-TKBS-0006-4 Revision No. 02 Effective Date: 06/05/2007 Page 18 of 56

4.2.1.4 Nonroutine Releases from the REDOX Plant

Ammonium nitrate flakes formed on the inside of the exhaust stack of the REDOX Plant and were 

released from 1952 through 1954. The largest release occurred in 1954. The flakes formed from the 

mixture of ammonia and nitrous oxides in the ventilation air. Volatile ruthenium oxide (RuO4) formed 

in an oxidation step in the plant, and it combined with the ammonium nitrate to form the flakes 

containing 103Ru and 106Ru. Some of the flakes were up to 10 cm in diameter, contained up to 200 

μCi (7.4 × 106 Bq) of ruthenium, and produced surface contact dose rates up to 20 rad/hr 

(1 Ci = 3.7 × 1010 Bq). Adley et al. (1953) and Greenfield (1954) reported the physical characteristics 

of the particles. Contact dose rates for 65.5% of the particles were in the range of 5 to 50 mrad/hr. 

The maximum deposition density occurred within about 400 m of the stacks and was 2 to 5 

particles/100 m2 (Parker 1954, 1956). These releases exposed military and other personnel on the 

site (Johnson 1954).

Table 4-4 is a summary of the physical, chemical, and radiological properties of radioactive particles 

released from Hanford from 1945 to 1956 and includes releases from T, B, and REDOX Plants. 

Figure 4-7 shows the monthly 106Ru releases from the REDOX plant (Till et al. 2002). 

100

101

102

103

104

105

GM

95th %-ile

Year

1952 1953 1954 1955

0.27

0.027

2.7

27

270

Estimated

release (Ci)

Estimated monthly release (GBq)

Figure 4-7. Estimated releases of 106Ru from REDOX Plant (Till et al. 

2002).

4.2.1.5 Releases of Tritium from 108-B 

Between 1949 and 1954, the Hanford Site produced tritium for the early weapons development 

period; the tritium was extracted in the 108-B facility from targets irradiated in the Hanford reactors. 

The product tritium was collected in flasks and sent to Los Alamos in gaseous diatomic form (T2). The 

facility initially had a roof vent about 75 ft off the ground, and eventually all building and hood air was 
Document No. ORAUT-TKBS-0006-4 Revision No. 02 Effective Date: 06/05/2007 Page 19 of 56

exhausted to a 300-ft stack (Heeb and Gydesen 1994). Heeb and Gydeson (1994) estimated the 

releases from both routine operations and process upsets and Gydesen described the uncertainty in 

the releases using a uniform distribution ranging from 0.222 to 1.778 times the central estimate. For 

the purposes of propagating the uncertainty in this dose reconstruction, the uncertainty has been 

approximated as a standard deviation of 40% of the central estimate. Table 4-5 lists the total annual 

releases and standard deviations.

Table 4-5. Annual amount of tritium 

released from 108-B. 

Year

Tritium 

released (Ci)

Standard 

deviation (Ci)

1949 683 273

1950 6,134 2,455

1951 27,060 10,824

1952 39,737 15,895

1953 3,911 1,564

1954 122,728 49,091

The releases were primarily elemental tritium. Elemental tritium slowly oxidizes to tritiated water 

(HTO and T2O) in the atmosphere. If dose reconstruction inhalation estimates are made with dose 

conversion factors for tritiated water, the level of conservatism will range from factors between 1 and 

1,000 [7]. 

4.2.2

Beginning in 1946 beta activity was monitored on air filters to measure 131I concentrations in air 

(Singlevich 1948), and alpha monitoring began in 1951 (Anderson and Soldat 1956). The reported 

values are of limited use because the atmospheric releases from weapons testing in the 1950s 

contributed to activity on the environmental filters that was not associated with operations at the 

Hanford Site. However the measured activities are useful as a check on the atmospheric dispersion 

calculations used to calculate occupational environmental doses [8]. 

Environmental Air Monitoring

4.2.3

The RATCHET computer program and an Excel® spreadsheet were used to calculate favorable to 

claimant but realistic intakes from airborne radionuclides. [Hcalc (Till et al. 2002) was not used

because Hcalc calculates worst-case or maximum hypothetical dose rather than a realistic dose.] 

Examples of the conservative overbiasing in the Hcalc program include:

Intake of Airborne Radionuclides 

• The program neglects plume rise at the point of release of radionuclides to the atmosphere. 

Without plume rise the program overestimates air concentrations and deposition on vegetation 

and soil near the point of release.

• The program neglects plume depletion caused by wet and dry deposition. Without plume 

depletion this program overestimates air concentrations and deposition on vegetation and soil.

• The program overestimates the radionuclides concentrations in the shallow surface soil and 

the external gamma dose because the program neglects leaching. 

• The program assumes a 12-yr buildup of radionuclides in the root zone of soil rather than the 

NCRP (1996) default value of 30 yr. The smaller buildup maximizes root uptake for the food 
Document No. ORAUT-TKBS-0006-4 Revision No. 02 Effective Date: 06/05/2007 Page 20 of 56

ingestion pathway. The work scope for the Hanford site profile specifically excludes the food 

pathway. 

The computer file srclist.dat from Till et al. (2002) provided the initial source terms in the spreadsheet. 

That file was based on the extensive research performed by Heeb (1994). Till et al. (2002) provides

monthly release estimates for the period from Hanford Site startup in 1944 through 1961. These files 

were extended to Hanford facility shutdown dates using the data from Heeb (1994) and augmented 

with the revisions to the 131I releases by Napier (2002). Minor releases in the 1980s were added as 

reported in the Hanford Site annual reports for those years. The 41Ar source terms for the reactors 

from Till et al. (2002) were extended through the date when each reactor was shut down using the 

approach used in that report. The 239Pu releases from the Z Plant were also extended using the 2-mo

lag time approximation of Till et all (2002). Because of differences in estimating atmospheric transport 

described below, emissions were tabulated as particulate, iodine, and noble gases. The following 

radionuclides were evaluated:

• 41Ar

• 144Ce144Pr

• 137Cs137Ba

• 3

H

• 131I131mXe

• 239Pu

• 103Ru103mRh

• 106Ru106Rh

• 90Sr90Y

• 95Zr95Nb

Annual emissions were evaluated for the following sources:

• T Plant particles

• B Plant particles

• REDOX Plant particles

• PUREX Plant particles

• Z Plant particles

• T Plant iodine

• B Plant iodine

• REDOX Plant iodine

• PUREX Plant iodine

• B & C Reactor noble gas

• KE & KW Reactors noble gas

• N Reactor noble gas

• D & DR Reactors noble gas

• H Reactor noble gas

• F Reactor noble gas

• 108-B elemental tritium

Uncertainties in the source term were described using an “uncertainty factor” in Heeb (1994). These 

factors represent the ratio of the 95th percentile to the 50th percentile; if the distribution is assumed to 

be lognormal the “uncertainty factor” may be converted into a geometric standard deviation (GSD) 

using the equation (Till et al. 2002)
Document No. ORAUT-TKBS-0006-4 Revision No. 02 Effective Date: 06/05/2007 Page 21 of 56





 



















 = 645.1

1

50th percentile

95th percentile GSD

The geometric standard deviation may be related to the more-conventional standard deviation through 

additional manipulation. Tables A-1 to A-9 in ATTACHMENT A list the source terms along with the 

uncertainties expressed as a standard deviation. Some uncertainties in the 1980s were approximated 

as the standard deviation equal to 10% of the measured values. Table A-10 lists atmospheric 

dispersion factors with uncertainties as standard deviations. The RATCHET computer program 

(Ramsdell, Simenon, and Burk 1994) was used to calculate annual average atmospheric dispersion 

coefficients. The RATCHET code was run for unit releases of 1-μm particles, noble gases, and iodine

speciated as a combination of elemental iodine, particle-bound iodine, and organic iodine as 

described in Farris et al. (1994). Hourly observations of wind speed, direction, stability, and 

precipitation from the extensive Hanford network of meteorological monitoring stations were used as 

input to the code. Results were calculated for monthly intervals from 1993 through 2002. A dense 

calculation output grid of 41 by 53 nodes on 1-km centers was used for all release points. Output was 

integrated to give total integrated exposure in units of Bq-s/m3 per Bq released. These normalized 

values were then averaged over the 10-yr observation period to provide monthly averages and 

standard deviations, which were then further rolled up into annual averages and standard deviations, 

which are listed in Table A-10 in ATTACHMENT A [9]. The dose reconstructor can calculate intakes 

for different source terms than those in Tables A-1 through A-9 by multiplying the atmospheric 

dispersion coefficient in Table A-10 by the source term in becquerels. 

Thirty-eight potential receptor locations were selected to represent exposure locations on the Hanford 

Site (see Figure 4-1). Table 4-6 lists these locations along with the east-west and north-south node 

identifiers from the computational grid [10]. 

Table 4-6. Selected receptor locations with identifying computational nodes [11]. 

Receptor location E-W Node N-S Node Receptor location E-W Node N-S Node

T Plant 12 30 200 Firestation 15 29

B Plant 20 29 100 Firestation 17 38

REDOX Plant 11 28 HMS Tower (622) 14 30

PUREX Plant 20 29 Columbia Camp 26 10

Z Plant 11 29 North Richland 38 6

B & C Reactors 9 37 300 Area 38 9

KW & KE Reactors 13 39 1100 Area 37 3

N Reactor 16 43 EOC/ALE Hq 19 10

D & DR Reactors 18 45 Hanford Townsite 31 32

H Reactor 22 46 Waste Disposal Site 26 21

F Reactor 25 41 WNP2 Region 34 21

200 N 12 34 FFTF Region 31 14

Midway (Riverland) 3 38 Army H-61 8 32

West Waluke 11 46 Army H-51 8 26

North Waluke 21 49 Army H-42 18 22

East Waluke 27 46 Army H-40 20 28

Yakima Barricade 4 32 Army H-50 8 28

Prosser Barricade 28 11 200E Guard House 19 28

Wye Barricade 29 21 200W Guard House 12 30
Document No. ORAUT-TKBS-0006-4 Revision No. 02 Effective Date: 06/05/2007 Page 22 of 56

The atmospheric dispersion factors for each location were multiplied by the emission rates from each 

source by radionuclide for each year from 1944 through 2001, even though the emissions from the 

reactors or the chemical separations plants after 1988 were minimal. The resultant annual air 

concentrations were then multiplied by 2,400 m3

/yr, which is the recommended breathing rate by 

reference man doing light work of 1.2 m3

/hr times a use factor of 2,000 hr/yr (ORAUT 2003). A 

standard deviation of 0.4 m3

/hr was assigned to this breathing rate. The final intake results in Table 

A-12 provide the annual intakes in becquerels per year for the maximum median receptor location by 

year and by radionuclide. Table 4-7 lists the maximum intake values by radionuclide.

Table 4-7. Maximum intakes by radionuclide. 

Radionuclide Maximum intake (Bq)

Ce-144 6.64E+01

Cs-137 2.35E+00

H-3 1.15E+05

I-131 1.04E+05

Pu-239 1.47E-02

Ru-103 5.84E+02

Ru-106 1.93E+02

Sr-90 2.67E+00

Zr-95 7.92E+01

In a similar fashion, the annual exposures for air submersion in 41Ar were adjusted for 2,000 hr/yr

occupancy. Those exposure values in becquerel-seconds per cubic meter were multiplied by the 

dose factor 6.15 × 10-14 Sv/Bq-s/m3

 (Eckerman et al. 1999) to give the submersion doses in sieverts in 

Table A-11 (1 Sv = 100 rem). Similarly the annual exposures from 41Ar were multiplied by the dose 

factor 1.01 × 10-13 Sv/Bq-s/m3

 (Eckerman et al. 1999) to give the skin beta-gamma dose in sieverts in 

Table A-11. The maximum 41Ar submersion dose was 3.47 × 10-5 Sv, and the maximum 41Ar beta 

skin dose was 5.7 × 10-5 Sv. 

4.3 EXTERNAL DOSE

4.3.1

The chemical separations plants began operations in April 1945. Quarterly environmental monitoring 

reports published from 1945 to 1955 and annual environmental reports published since 1956 present 

gamma exposure levels at various locations throughout the Hanford Site. Up through 1953 radiation 

exposure measurements were reported in milliroentgen, millirep, and subsequently in millirad. Hanf 

and Thiede (1994) stated that the difference in deposited energy in tissue between units is so small 

that the units can be considered nearly identical. The data in Singlevich (1948) summarized the 

measured natural background radiation levels between 1946 and 1948 as 0.3 to 0.5 mrad/d. For this 

document, the natural gamma background radiation level attributed to cosmic radiation and naturally 

occurring radioactive materials in the environment was assumed to be 0.4 mrad/d or 146 mrad/yr. 

The background was not subtracted from the ambient readings [12]. 

Ambient Radiation

Figure 4-8 illustrates that external gamma radiation attributed to site operations in the chemical 

separations area (200-East) averaged 0.4 mrad/d above background levels and that the maximum 

exposures occurred in 1945 and 1946. The external gamma exposure levels measured near the 

reactors were near natural background levels (Singlevich 1948). Levels were measured by 

detachable C chambers; at 200-East (separations area), levels averaged roughly twice those at 100-B 

(a reactor area). The average level at 100-B was 0.35 mrep/24 hr, which is within the stated 

background range of the instrument (0.3–0.5 mrep/24 hr), and the average level at 200-East was 0.75 

mrep/24 hr (Singlevich 1948) (Till et al. 2002). 
Document No. ORAUT-TKBS-0006-4 Revision No. 02 Effective Date: 06/05/2007 Page 23 of 56

0.0

0.2

0.4

0.6

0.8

1.0

1.2

1.4

1.6

1.8

2.0

10/10/4510/31/4511/21/4512/12/45

1/2/462/6/46

3/13/46

4/3/46

4/24/465/15/46

6/5/46

6/26/467/17/46

8/7/46

8/31/46

10/15/4611/30/46

1/15/472/28/474/15/475/31/478/31/47

11/30/47

2/28/485/31/488/31/48

11/30/48

End of sampling interval

mrep per 24 hours

200-E

100-B

Figure 4-8. Radiation levels at two locations, 1945 to 1948.

Figure 4-9 illustrates the exposure rates measured near the REDOX Plant and the closest residence 

locations to REDOX, which were military sites H-50, H-51, and H-61 (Irish 1955). Measured exposure 

rates at the REDOX perimeter are the highest of all environmental stations monitored between 1945 

and 1955. Monitoring at the perimeter was discontinued in December 1954, but monitoring continued 

in the REDOX area (Till et al. 2002).

0.1

1

10

100

Aug-50

Oct-50

Dec-50

Feb-51

Apr-51

Jun-51

Aug-51

Oct-51

Dec-51

Feb-52

Apr-52

Jun-52

Aug-52

Oct-52

Dec-52

Feb-53

Apr-53

Jun-53

Aug-53

Oct-53

Dec-53

Feb-54

Apr-54

Jun-54

Aug-54

Oct-54

Dec-54

Feb-55

Apr-55

Jun-55

Aug-55

Oct-55

Dec-55

Month and year

mrep or mrad per day

Redox perimeter

Redox area

PSN 300 (aka H-61)

PSN 310 (aka H-51)

PSN 320 (aka H 50)

PSN330 (aka H-40)

Note logarithmic scale

Figure 4-9. Exposure rates measured near the REDOX Plant and at 

four military installations. 
Document No. ORAUT-TKBS-0006-4 Revision No. 02 Effective Date: 06/05/2007 Page 24 of 56

Figure 4-10 illustrates the relationship between 131I and 106Ru releases per year as well as the net 

radiation exposures levels measured between the REDOX Plant perimeter and the 200 areas. The 

net gamma exposure rates are mainly due to the 131I and 106Ru releases. The principal gamma ray 

from 131I is 0.364 MeV emitted 82% of the time. The principal gamma rays from 106Ru are from its 

progeny 106Rh and are 0.512 MeV emitted 21% of the time and 0.622 MeV emitted 11% of the time. A 

measured background exposure rate of 0.4 mrep/d was subtracted from the onsite exposure rate 

measurements to obtain net exposure rates (Till et al. 2002).

0

100

200

300

400

500

600

1945 1946 1947 1948 1949 1950 1951 1952 1953 1954 1955

Year

kCi I-131 or Ci Ru-106 released

0

5

10

15

20

25

Net expposure rate (mrep or mrad per day)

kCi I-131 released (mean estimate)

Ci Ru-106 released (mean estimate)

Net exposure rate at REDOX perimeter

(Gross-0.4)

Net exposure rate between 200 Areas

(Gross Annual Ave. - 0.4)

Figure 4-10. Time trends in annual 131I and 106Ru releases to air with net 

exposure rates between the 200 Areas (Building 622) and at the REDOX 

plant perimeter. 

Table 4-8 lists the external gamma measurements at Hanford from 1944 through 2001 including 

fallout and background. The values are average values in millirem per year for exposures of 2,000 

hr/yr. Blank values in the table indicate that measurements were not available for those years. 

4.3.2

4.3.2.1 Xenon

Releases of Noble Gases

The relative dose contribution of 133Xe to 131I can be estimated by comparing the products of the 

release rates and the dose conversion factors. At its peak in 1945 the 133Xe release rate was 42,000 

Ci/mo. The increase in fuel element cooling time that began in 1946 resulted in more than a 10-fold 

reduction in 133Xe releases to the atmosphere that continued in subsequent years. The 131I release 

rate at the peak 133Xe release rate was 89,000 Ci/mo. The dose conversion factors for 133Xe and 131I 

are 4.3 × 10-8 and 2.4 × 10-4 Sv/Bq/m3

, respectively. Comparing the products of the release rate and 

the dose conversion factor for each radionuclide, the 131I contribution to the dose was more than 

10,000 times larger than that from 133Xe (Till et al. 2002). Therefore, 131I is listed as a major 

contributor to the occupational environmental dose and 133Xe is not. 
Document No. ORAUT-TKBS-0006-4 Revision No. 02 Effective Date: 06/05/2007 Page 25 of 56

Table 4-8. External gamma radiation (mrem/yr) [13]. 

300 

Area 

400 Area/

FFTF 

Hanford 

Townsite

Columbia 

Camp

Prosser 

Barricade ALE Wahluke

WNP2 

Region 

Wye 

Barricade

Yakima 

Barricade

Army 

Loop

1945 170 149

1946 69 41

1947 121 88

1948 76 115

1949 60 158

1950 49 32

1951 49 32

1952 96 15

1953 35 23

1954 24 31

1955 84 76

1956 160 126

1957 269

1958

1959

1960a,c 80 30 30 30 30 30 30 30 30 30 30

1961a,c 80 30 30 30 30 30 30 30 30 30 30

1962a,c 80 39 39 39 39 39 39 39 39 39 39

1963a,d 46 39 39 39 39 39 39 39 39 39 39

1964a,d 46 34 34 34 34 34 34 34 34 34 34

1965a,d 46 27 27 27 27 27 27 27 27 27 27

1966 39 30 44 30 30 30 30 30 30 30 30

1967 40 49

1968 39 35

1969 80

1970 31 13

1971 17 16 13 15 16 13 16

1972 21 19 17 18 20 16 22

1973 18 16 16 17 17 17 16 17

1974 17 16 15 17 17 17 16 18

1975 17 16 15 16 17 17 16 17

1976 16 16 15 16 17 16 16 17

1977 16 16 15 16 16 17 15 17

1978 15 16 15 16 16 16 16 17

1979 16 16 16 17 18 18 17 18

1980 19 16 16 17 17 17 16 18

1981 29 16 16 18 18 17 17 18

1982 121 16 17 17 18 18 17 18

1983 98 17 16 16 16 18 18 17 18 17

1984 21 17 16 15 16 17 18 17 18 16

1985 19 14 13 14 15 16 16 16 15 16 15

1986 21 16 12 16 17 17 16 15 14 17 16

1987 21 18 17 18 19 20 19 18 18 21 19

1988 19 19 18 20 20 21 20 19 18 21 20

1989 20 20 19 19 20 21 20 23 18 23 21

1990 19 19 19 18 17 20 20 20 19 20 19

1991 22 21 21 21

1992 22 22 22 21

1993 21 23 20 22

1994 24 24 24 24

1995 19 19 20 19

1996 18 19 20

1997 18 19 19

1998 19 19 20 21 19 19 21 19

1999 19 19 20 20 22 21 21 20 22 20

2000 19 19 17 20 20 20 20 19 22 19

2001 19 19 18 21 22 21 20 20 22 20
Document No. ORAUT-TKBS-0006-4 Revision No. 02 Effective Date: 06/05/2007 Page 26 of 56

100 Area 

Fire Station 100 B 100 D 100 F 100 K 100 N 100 H

1100 

Area 

200 

East 

200 

West 200 N

1945 127 135 123 194 185

1946 47 33 38 122 50

1947 42 60 85 115 57

1948 24 52 76 67 30

1949 31 17 38 25 16 20

1950 55 44 40 37 37 45

1951 55 44 40 37 37 45

1952 35 31 19 33 13 37

1953 48 33 34 38 49 63

1954 88 119 71 133 71 217

1955 38 95 253 87 35 178 265

1956 347 216 258 37 242 230

1957b 146

1958b 319

1959b 173

1960c 111 99 127 87 55 98 143

1961c 111 99 127 87 55 98 143

1962c 111 99 127 87 55 98 143

1963d 30 53 45 52 118 76 46 30 64 45 30

1964d 30 53 45 52 118 76 46 30 64 45 30

1965d 30 53 45 52 118 76 46 64 45 30

1966 30 53 48 44 108 56 39 30 66 56 30

1967 60 47 75 125 69 53 69 41

1968 63 47 49 157 95 46 42 41

1969 62 55 69 125 83 103 57

1970 29 29 24 74 39 31

1971 17 16 17 31 30 17

1972 17 19 24 34 30 21

1973 16 18 18 17 37 37 21

1974 16 17 18 17 22 33 22

1975 18 17 17 17 22 31 21

1976 16 17 15 15 19 27 18

1977 15 16 15 14 20 27 19

1978 16 17 15 21 15 22 20

1979 16 18 16 21 14 22 21

1980 16 17 15 20 14 22 18

1981 17 17 15 20 14 21 18

1982 16 17 17 21 14 21 17

1983 17 17 15 21 15 17 18

1984 16 18 17 21 15 17

1985 13 15 13 18 14 14 16

1986 15 16 13 20 14 16 16

1987 18 19 17 20 17 19 19

1988 18 20 17 21 18 19 20

1989 19 19 18 21 20 20 20 20

1990 19 19 18 21 17 17 20 19

1991 27 19 23 19 20 21 21

1992 21 20 24 20 22 22 23

1993 23 19 23 19 22 23 23

1994 25 22 28 22 24 25 26

1995 20 16 17 19 19 20

1996 20 16 17 19 19 20

1997 20 16 16 19 18 20

1998 20 17 17 19 19 21

1999 20 20 16 17 20 20 22

2000 19 19 17 17 19 19 21

2001 20 20 18 19 20 19 21

a. Based on the annual average dose rate for entire Hanford Site as reported in annual reports, except for 100, 200, and 300 Areas.

b. Based on monthly reports where dose rate ranges (max and min) were reported for “Separations Area” and “Residential Area” only. Maximum 

dose rate reported here.

c. Based on an average of 1952-1956 gamma levels at the 100, 200, and 300 Areas.

d. Based on an average of 1966-1970 gamma levels at the 100, 200, and 300 Areas.
Document No. ORAUT-TKBS-0006-4 Revision No. 02 Effective Date: 06/05/2007 Page 27 of 56

4.3.2.2 Argon Releases from the Production Reactors

Argon-41 was released from the Hanford reactors as a neutron activation product of stable argon in 

air and not from the chemical separations facilities. Effluent concentrations were measured for only 

brief periods over the years, and the reactors did not operate continuously. Despite those problems 

Till et al. (2002) created percentiles from the distributions of monthly releases of 41Ar, which Table 4-9 

lists. Table 4-10 lists the 41Ar concentrations in the reactor stacks along with stack flow rates.

Table 4-9. Distributions of monthly release estimates for 41Ar from reactors 

and Areas (Till et al., 2002).

Reactor

Percentiles of distributions of release estimates

(Ci/mo) for individual reactors and areas with two reactors

5th 25th 50th 75th 95th

B, D, or F 320 1,200 2,200 3,300 4,100

C 4,000 5,600 7,000 8,700 11,000

B and Ca 5,600 7,600 9,300 11,000 14,000

DR 5,900 6,600 7,600 8,500 9,400

D and DRb 7,100 8,600 9,800 11,000 13,000

H 5,700 7,000 8,600 10,000 12,000

KE 4,200 5,900 7,400 9,100 12,000

KW 4,100 5,600 7,000 8,700 11,000

KE and KWc 10,000 13,000 15,000 17,000 20,000

a. Both reactors operated in the same area after November 1952.

b. Both reactors operated in the same area after October 1950.

c. Both reactors operated in the same area after April 1955.

Table 4-10. Concentrations of 41Ar measured in effluent flow rates for production 

reactor stacks (Till et al. 2002). 

Reactor Nb

Measured concentration (μCi/m3) of 41Ara Stack effluent

flow rate (m3/s)c Average Maximum

B 0 20 39 47

D 4 23 39 47

F 0 17 27 47

DR 11 80 110 40

C 3 <4 <4 64

H 8 48 66 76

KE d d d 67

KW d d d 64

a. Argo-41 concentration data from Paas (1953a).

b. Number of samples collected (Paas 1953a,b). 

c. Based on flow rates given in Heeb (1994). 

d. The reactor was not operating at the time of the measurements.

4.3.3

Emissions of particles of greater than respirable size occurred from 1947 through 1948 from T and B 

Plants and from 1952 through 1955 from the REDOX Plant. The releases from T and B Plants were 

relatively continuous, having been caused by deposition of radioactive mists on the insides of metal 

ductwork, which resulted in corrosion and the release of small iron particles coated with radioactive 

material. The releases from REDOX were more episodic, although one of the mechanisms was 

similar (i.e., accumulation and release of radionuclides on ductwork) [14]. 

Skin Deposition of Airborne Particulate Emissions
Document No. ORAUT-TKBS-0006-4 Revision No. 02 Effective Date: 06/05/2007 Page 28 of 56

Total releases from aged fission products carried on particles from T and B Plants totaled from 20 to 

100 Ci/mo each. The average particle contained about 1.1 μCi (Till et al. 2002), so between about 40 

to 180 million particles were emitted per month from about September 1947 through April 1948, when 

sand filters were installed to stop the release (Cleavenger and Gydesen 1989). The greatest activity 

measured on a T or B Plant particle was 3.2 μCi; therefore, assuming a 5 μCi particle would be 

favorable to claimants. 

Notable from REDOX were the large ammonium-sulfate flakes containing 103Ru and 106Ru that were 

emitted from REDOX in March 1952 (Ebright 1954). The median estimate for the total release activity 

was 145 Ci (5.37 TBq). An estimated 290 million particles were released. Somewhat smaller 

releases occurred from REDOX in April, June, and September 1952, August and September 1953, 

and January, April, May, and June 1954. REDOX ruthenium particles generally contained less than 

300 μCi (1.11 × 107 Bq) 106Ru and 170 μCi (6.29E6 Bq) 103Ru. The estimated skin dose rate was 

1,300 to 2,400 rads/hr.

Based on binomial and Poisson distribution theory, the probability that an individual would encounter 

one or more released particles on their skin is almost one (Till et al. 2002). Till et al. (2002) calculated 

the number of radioactive particles from the REDOX Plant that would fall on a person at different 

locations during the 1950s. The values ranged from 100 particles for a person in Richland to 830 

particles at military location H-50. Because the numbers are maximum values for 24-hr occupancy 7 

days a week, the numbers should be multiplied by the use factor of 0.1 to provide a realistic favorable 

to claimant number of particles. The use factor was developed as follows: If one assumes that an 

individual worked 8 hr/d 5 d/week, the use factor would be 40 work hours divided by 168 hr/week or 

0.24. If the worker was indoors, exposures could be reduced by factors of up to 10. Therefore, a use 

factor of 0.1 is favorable to claimants. Using the 0.1 use factor, the greatest number of particle 

encounters at any of the military camps is 83 particles from March 1952 through June 1954 at military 

location H-50. 

Table 4-11 lists the probability that an individual would be exposed to one or more particles from T 

and B Plants in the period from 1947 to 1948 for various locations assuming a use factor of 0.1. 

Similarly, Table 4-12 lists the probability that an individual would be exposed to one or more particles 

from REDOX in the period from 1952 to 1954 for various locations [15]. It can be seen that for an 

individual in most locations who was present throughout the periods of interest, the likelihood of 

encountering at least one particle is essentially 100%.

Table 4-13 presents the dose coefficients for different radionuclides attached to or contained in the 

particles released to the air. Assuming 5 μCi (1.85 × 105 Bq) particles released as iron particles in the 

1940s from T and B Plants, such a particle would have a localized skin dose rate of 11 to 32 rads/hr. 

For the REDOX ruthenium particles containing 300 μCi (1.11 × 107 Bq) 106Ru and 170 μCi 

(6.29E × 106 Bq) 103Ru released in the 1950s, the estimated skin dose rate is 1,300 to 2,400 rads/hr.

Jones, Mansfield, and Bell (1998) obtained retention half-lives of particles deposited on skin that were 

between 1 and 3 hr. This translates to a mean residence time (T1/2 ÷ ln 2) of 1.4 to 4.3 hr (Whicker 

and Schultz 1982).

Similar calculations have been done to evaluate the likelihood of inhalation of airborne large 

radioactive particles or of the ingestion of a large radioactive particle that deposits on the skin. For 

both of these potential pathways, the maximum combined likelihood from all releases is less than 0.01 

for all Hanford locations, and is generally less than 0.001 for individual months. Therefore, these 

pathways have not been included in the dose reconstruction. 
Document No. ORAUT-TKBS-0006-4 Revision No. 02 Effective Date: 06/05/2007 Page 29 of 56

Table 4-11. Probability of interaction of an individual with at least one T- or B-Plant 

particle by receptor location and by month for a 10% use factor [16]. 

Receptor 9/47 10/47 11/47 12/47 1/48 2/48 3/48 4/48 Total

T Plant 0.78 0.95 0.98 0.98 0.98 0.95 0.79 0.53 1.00

B Plant 0.90 0.99 1.00 1.00 1.00 0.99 0.90 0.67 1.00

REDOX 0.55 0.78 0.85 0.85 0.86 0.79 0.55 0.32 1.00

PUREX 0.79 0.95 0.97 0.97 0.97 0.95 0.78 0.51 1.00

Z Plant 0.62 0.84 0.90 0.90 0.91 0.85 0.62 0.37 1.00

B/C Reactor 0.30 0.49 0.57 0.57 0.57 0.50 0.30 0.15 0.99

KW/KE Reactors 0.36 0.58 0.66 0.66 0.66 0.59 0.36 0.19 1.00

N Reactor 0.38 0.60 0.68 0.68 0.69 0.61 0.38 0.20 1.00

D/DR Reactor 0.32 0.53 0.60 0.60 0.61 0.53 0.32 0.17 0.99

H Reactor 0.29 0.49 0.56 0.56 0.57 0.50 0.29 0.15 0.99

F Reactor 0.34 0.55 0.63 0.63 0.63 0.56 0.34 0.18 1.00

200 N 0.39 0.62 0.70 0.70 0.70 0.63 0.39 0.21 1.00

Midway 0.17 0.30 0.36 0.36 0.36 0.31 0.17 0.09 0.92

West Wahluke 0.28 0.47 0.54 0.54 0.55 0.48 0.28 0.14 0.99

North Wahluke 0.21 0.36 0.42 0.42 0.43 0.37 0.21 0.10 0.96

East Wahluke 0.23 0.39 0.46 0.46 0.47 0.40 0.23 0.12 0.97

Yakima Barricade 0.17 0.30 0.35 0.35 0.36 0.30 0.17 0.08 0.92

Prosser Barricade 0.28 0.47 0.54 0.54 0.55 0.48 0.28 0.14 0.99

Wye Barricade 0.42 0.65 0.72 0.73 0.73 0.66 0.42 0.23 1.00

200 Fire 0.72 0.91 0.95 0.95 0.95 0.92 0.72 0.46 1.00

100 Fire 0.37 0.59 0.67 0.67 0.67 0.60 0.37 0.20 1.00

HMS 0.63 0.85 0.91 0.91 0.91 0.86 0.63 0.38 1.00

Columbia Camp 0.23 0.40 0.47 0.47 0.47 0.41 0.23 0.12 0.97

North Richland 0.23 0.39 0.46 0.46 0.46 0.40 0.23 0.11 0.97

300 Area 0.22 0.38 0.44 0.44 0.45 0.38 0.22 0.11 0.96

1100 Area 0.24 0.41 0.48 0.48 0.48 0.42 0.24 0.12 0.98

EOC/ALE 0.10 0.19 0.23 0.23 0.23 0.19 0.10 0.05 0.77

Hanford Townsite 0.30 0.50 0.57 0.57 0.58 0.50 0.30 0.16 0.99

Waste Disposal Area 0.48 0.72 0.79 0.79 0.79 0.72 0.48 0.27 1.00

WNP2 0.31 0.51 0.59 0.59 0.59 0.52 0.31 0.16 0.99

FFTF 0.30 0.50 0.58 0.58 0.58 0.51 0.30 0.16 0.99

H-61 0.30 0.51 0.58 0.58 0.59 0.51 0.31 0.16 0.99

H-51 0.24 0.41 0.48 0.48 0.49 0.42 0.24 0.12 0.98

H-42 0.34 0.55 0.63 0.63 0.64 0.56 0.34 0.18 1.00

H-40 0.82 0.96 0.98 0.98 0.98 0.97 0.82 0.56 1.00

H-50 0.25 0.43 0.50 0.50 0.50 0.43 0.25 0.13 0.98

200E Guardhouse 0.77 0.94 0.97 0.97 0.97 0.95 0.77 0.50 1.00

200W Guardhouse 0.78 0.95 0.98 0.98 0.98 0.95 0.79 0.53 1.00
Document No. ORAUT-TKBS-0006-4 Revision No. 02 Effective Date: 06/05/2007 Page 30 of 56

Table 4-12. Probability of interaction of an individual with at least one REDOX particle by receptor 

location and by month for a 10% use factor [17]. 

Receptor

Mar52Apr52Jun52Sep52Aug53Sep53Jan54Apr54May54Jun54 Total

T Plant 0.95 0.20 0.00 0.01 0.01 0.87 0.99 0.00 0.01 0.00 1.00

B Plant 0.84 0.12 0.00 0.01 0.01 0.70 0.93 0.00 0.00 0.00 1.00

REDOX 1.00 0.88 0.02 0.10 0.12 1.00 1.00 0.03 0.07 0.01 1.00

PUREX 0.84 0.13 0.00 0.01 0.01 0.70 0.94 0.00 0.00 0.00 1.00

Z Plant 1.00 0.38 0.00 0.02 0.03 0.99 1.00 0.01 0.02 0.00 1.00

B/C Reactor 0.65 0.07 0.00 0.00 0.00 0.50 0.79 0.00 0.00 0.00 0.97

KW/KE Reactors 0.74 0.09 0.00 0.00 0.01 0.58 0.86 0.00 0.00 0.00 0.99

N Reactor 0.77 0.10 0.00 0.01 0.01 0.62 0.89 0.00 0.00 0.00 0.99

D/DR Reactor 0.70 0.08 0.00 0.00 0.01 0.55 0.84 0.00 0.00 0.00 0.98

H Reactor 0.66 0.08 0.00 0.00 0.00 0.51 0.80 0.00 0.00 0.00 0.97

F Reactor 0.74 0.09 0.00 0.00 0.01 0.58 0.86 0.00 0.00 0.00 0.99

200 N 0.77 0.10 0.00 0.00 0.01 0.62 0.89 0.00 0.00 0.00 0.99

Midway 0.48 0.05 0.00 0.00 0.00 0.35 0.62 0.00 0.00 0.00 0.88

West Wahluke 0.62 0.07 0.00 0.00 0.00 0.47 0.77 0.00 0.00 0.00 0.96

North Wahluke 0.52 0.05 0.00 0.00 0.00 0.38 0.66 0.00 0.00 0.00 0.91

East Wahluke 0.56 0.06 0.00 0.00 0.00 0.41 0.70 0.00 0.00 0.00 0.93

Yakima Barricade 0.60 0.06 0.00 0.00 0.00 0.45 0.74 0.00 0.00 0.00 0.95

Prosser Barricade 0.84 0.13 0.00 0.01 0.01 0.70 0.94 0.00 0.00 0.00 1.00

Wye Barricade 0.83 0.12 0.00 0.01 0.01 0.68 0.93 0.00 0.00 0.00 1.00

200 Fire 0.95 0.19 0.00 0.01 0.01 0.85 0.99 0.00 0.01 0.00 1.00

100 Fire 0.77 0.10 0.00 0.00 0.01 0.61 0.88 0.00 0.00 0.00 0.99

HMS 0.93 0.18 0.00 0.01 0.01 0.83 0.98 0.00 0.01 0.00 1.00

Columbia Camp 0.81 0.11 0.00 0.01 0.01 0.66 0.92 0.00 0.00 0.00 1.00

North Richland 0.60 0.06 0.00 0.00 0.00 0.46 0.75 0.00 0.00 0.00 0.95

300 Area 0.57 0.06 0.00 0.00 0.00 0.43 0.72 0.00 0.00 0.00 0.94

1100 Area 0.67 0.08 0.00 0.00 0.00 0.51 0.80 0.00 0.00 0.00 0.97

EOC/ALE 0.46 0.04 0.00 0.00 0.00 0.33 0.60 0.00 0.00 0.00 0.86

Hanford Townsite 0.69 0.08 0.00 0.00 0.01 0.53 0.82 0.00 0.00 0.00 0.98

Waste Disposal Area 0.94 0.18 0.00 0.01 0.01 0.84 0.98 0.00 0.01 0.00 1.00

WNP2 0.67 0.08 0.00 0.00 0.00 0.52 0.81 0.00 0.00 0.00 0.97

FFTF 0.78 0.10 0.00 0.01 0.01 0.63 0.89 0.00 0.00 0.00 0.99

H-61 0.79 0.11 0.00 0.01 0.01 0.65 0.90 0.00 0.00 0.00 0.99

H-51 0.87 0.14 0.00 0.01 0.01 0.74 0.95 0.00 0.01 0.00 1.00

H-42 0.96 0.21 0.00 0.01 0.01 0.89 0.99 0.00 0.01 0.00 1.00

H-40 0.88 0.14 0.00 0.01 0.01 0.75 0.96 0.00 0.01 0.00 1.00

H-50 0.90 0.15 0.00 0.01 0.01 0.78 0.97 0.00 0.01 0.00 1.00

200E Guardhouse 0.89 0.15 0.00 0.01 0.01 0.77 0.96 0.00 0.01 0.00 1.00

200W Guardhouse 0.95 0.20 0.00 0.01 0.01 0.87 0.99 0.00 0.01 0.00 1.00

Table 4-13. Dose coefficients for radionuclides contained in Hanford active particles (Till et al. 2002). 

Primary radionuclide 

and (decay product)

Fraction of beta activity for 

T and B Plant particles

Dose coefficient (nGy h–1 per Bq cm–2)

a

Skin depth of 0.07 mm Skin depth of 0.4 mm

Ru-103 0.13 568 28

Ce-141 0.14 1,538 169

Zr-95 (Nb-95) 0.06 1,288 86

Sr-89 0.14 1,667 887

Y-91 0.23 1,669 897

Ru-106 (Rh-106) 0.03 1,845 1,165

Ce-144 (Pr-144) 0.26 2,630 634

Sr-90 (Y-90) 0.05 3,133 1,384

Cs-137 0.05 1,432 384

a. Dose coefficients for distances along the axis of a circular source with area of 1 cm2 or a point source averaged over that area 

from Cross et al. (1992). Tabled values include contributions of radioactive decay products.
Document No. ORAUT-TKBS-0006-4 Revision No. 02 Effective Date: 06/05/2007 Page 31 of 56

4.4 ATTRIBUTIONS AND ANNOTATIONS

Where appropriate in the preceding text, bracketed callouts have been inserted to indicate 

information, conclusions, and recommendations to assist in the process of worker dose 

reconstruction. These callouts are listed in this section with information that identifies the source and 

justification for each item. Conventional references are provided in the next section that link data, 

quotations, and other information to documents available for review on the Oak Ridge Associated 

Universities (ORAU) Team servers.

Bruce Napier serves as a Site Expert for this document. As such, he is responsible for advising on 

site-specific issues and incidents as necessary and ensures the completeness and accuracy of the 

document. Because of his prior work experience at the site, he possesses, or is aware of information 

that is relevant for reconstructing radiation doses experienced by claimants who worked at the site. In 

all cases where such information or prior studies or writings are included or relied upon by the 

document owner, those materials are fully attributed. Mr. Napier’s Disclosure Statement is available 

at www.oraucoc.org.

[1] Napier, Bruce. Battelle Memorial Institute – Pacific Northwest Division (BMIPND). Principal 

Health Physicist. August 2006. 

Each of the different routes, or pathways, by which people can be exposed to radiation, result 

in exposures to different parts of the body. Health physicists must analyze the potential for 

and effects of exposure via each of the three basic pathways – inhalation, ingestion, and direct 

exposure – when calculating exposures or estimating the effects of exposures. For workers, 

the opportunity for ingestion of airborne material or local surface deposits in the occupational 

setting is small (no crops are grown on the Hanford Site), so the focus is on inhalation and 

external exposure, from immersion in contaminated air and from direct deposition of particles 

on the skin. 

[2] Napier, Bruce. BMIPND. Principal Health Physicist. August 2006. 

The listed workers were not considered to be radiation workers and thus did not have their

own personal dosimeters. 

[3] Napier, Bruce. BMIPND. Principal Health Physicist. August 2006. 

The specific locations for calculation were selected by B. A. Napier on the basis of 

geographical coverage, known release points, known occupied areas, and anticipated public 

interest.

[4] Napier, Bruce. BMIPND. Principal Health Physicist. August 2006. 

The chemical forms that are associated with the listed inhalation classes are those 

recommended in ICRP Publication 68, Annex F, for the calculation of inhalation dose 

coefficients (ICRP 1995) . The selection of the appropriate chemical form for a particular 

exposure is left to the dose reconstructor.

[5] Napier, Bruce. BMIPND. Principal Health Physicist. August 2006. 

The estimates of release of all gaseous and particulate radionuclides from the Hanford stacks 

followed the multiplicative steps initially elaborated by Heeb (1994).

[6] Napier, Bruce. BMIPND. Principal Health Physicist. August 2006. 

As reported in Till et al. (2002), the qualitative reports tabulated in Cleavenger and Gydesen

(1989) indicate that more difficulties with the new effluent treatment systems were experienced 

at B Plant.
Document No. ORAUT-TKBS-0006-4 Revision No. 02 Effective Date: 06/05/2007 Page 32 of 56

[7] Napier, Bruce. BMIPND. Principal Health Physicist. August 2006. 

The tritium was produced by neutron bombardment of lithium targets in the absence of 

oxygen. The resulting tritium would have been atomic and would have combined into HT or 

TT gas, not water. HT gas slowly oxidizes into water in the environment. The ratio of 

inhalation dose rate conversion factors for HTO to HT is 1,000. As the released material was 

transported downwind the initial doses would be almost entirely HT; at longer distances, the 

HTO component would increase.

[8] Napier, Bruce. BMIPND. Principal Health Physicist. August 2006. 

A discussion of the applicability of environmental monitoring to Hanford releases, and the use 

of the measurements as a validation of the modeling technique employed, is presented in 

Napier (2002). This reference also provides an extensive listing of the available historical 

documentation of environmental monitoring at Hanford.

[9] Napier, Bruce. BMIPND. Principal Health Physicist. August 2006. 

These activities were performed at Pacific Northwest National Laboratory by B. A. Napier and 

J. V. Ramsdell, Jr., in August 2003 to provide the necessary information to estimate doses via 

the atmospheric dispersion pathway.

[10] Napier, Bruce. BMIPND. Principal Health Physicist. August 2006. 

The specific locations for calculation were selected by B. A. Napier on the basis of 

geographical coverage, known release points, known occupied areas, and anticipated public 

interest.

[11] Napier, Bruce. BMIPND. Principal Health Physicist. August 2006. 

The specific locations for calculation were selected by B. A. Napier on the basis of 

geographical coverage, known release points, known occupied areas, and anticipated public 

interest.

[12] Napier, Bruce. BMIPND. Principal Health Physicist. August 2006. 

The background was not subtracted from the environmental measurements in compliance with 

the general guidance of ORAUT-PROC-0031, DOE Technical Basis Document Development, 

Review, and Approval Process (ORAUT 2006), Section 6.3.13.

[13] Napier, Bruce. BMIPND. Principal Health Physicist. August 2006. 

The external dose rate table was prepared by E. J. Antonio, B. A. Napier, and L. E. Bisping 

from the extensive collection of Hanford records. The dose rates for 1945 to 1949 are based 

on daily measurements using Integron devices. The dose rates for 1970 to 2001 are based on 

the Hanford environmental monitoring thermoluminescent dosimeter database. The dose 

rates for the intermediate period are based on individual measurements that were extracted 

from hundreds of Hanford Site monthly, quarterly, annual, and special reports from the DOE 

Reading Room at the Washington State University Tri-Cities library. 

[14] Napier, Bruce. BMIPND. Principal Health Physicist. August 2006. 

The Hanford reprocessing plants dissolved the uranium with nitric acid, separated the uranium 

and plutonium, and further processed the plutonium (all in the 200 Area facilities). Particularly 

in the chemical processes in the 200 Area facilities, radioactive gases, mists, and fumes were 

generated. In the early years, these were vented directly to the 200-ft exhaust stacks via 

metal ducting. In T- and B-Plants in the 1940s, these chemically reactive mists corroded the 

ductwork, which resulted in the emission of rust particles contaminated with a fraction of the 

radionuclides. These particles deposited near the emission points (i.e., near the foot of the 
Document No. ORAUT-TKBS-0006-4 Revision No. 02 Effective Date: 06/05/2007 Page 33 of 56

stacks) and were detected as a result of recurrent personnel contamination in the vicinity 

(Parker 1948b, p. 4). Even at that time, the particle emission was recognized as symptomatic 

of the larger overall releases (e.g., Parker 1948b, p. 2). The particulate problem that began at 

REDOX in the early 1950s was of similar origin. When the dichromate head-end process was 

replaced with the permanganate process in 1953, the enhanced volatilization of ruthenium 

resulted in increased environmental release up the stack. Together with chemical reactions in 

the exhaust ducting and stack, this also created the conditions for evolution of a rutheniumcontaminated ammonium nitrate film that lined the ducts and stack. Under certain conditions, 

this film would break loose and blow as relatively large particles (up to several centimeters 

diameter) up the stack.

[15] Napier, Bruce. BMIPND. Principal Health Physicist. August 2006. 

Tables 4-11 and 4-12 were prepared by B. A. Napier using the methods of Till et al. (2002) 

and additional Hanford-specific data. 

[16] Napier, Bruce. BMIPND. Principal Health Physicist. August 2006. 

Table 4-11 was prepared by B. A. Napier using the methods of Till et al. (2002) and additional 

Hanford-specific data.

[17] Napier, Bruce. BMIPND. Principal Health Physicist. August 2006. 

Table 4-12 was prepared by B. A. Napier using the methods of Till et al. (2002) and additional 

Hanford-specific data.
Document No. ORAUT-TKBS-0006-4 Revision No. 02 Effective Date: 06/05/2007 Page 34 of 56

REFERENCES

Adley, F. E., 1948, report of a Study of the Fate of the 200 Area Stack Gases, HW-9864, General 

Electric Company, Hanford Atomic Products Operation, Richland, Washington, May 21.

Adley, F. E., W. E. Gill, H. B. Perry, R. H. Scott, and D. E. Wisehart, 1953, Particles Emitted by 291-S 

Stack, report to D. W. Pearce, HW-28780, General Electric Company, Hanford Works, 

Richland, Washington, July 22.

Adley, F. E., J. J. Fuquay, W. E. Gill, R. H. Scott, and D. E. Wisehart, 1954, REDOX Stack Gas 

Particles, 1954, HW-32209, General Electric Company, Hanford Works, Richland, 

Washington, November 10.

Anderson, B. V., and J. K. Soldat, 1956, Radioactive Contamination in the Hanford Environs for the 

Period April, May, June 1956, HW-42215, General Electric Company, Hanford Atomic 

Products Operation, Richland, Washington, August 7.

Ballinger, M. Y., and R. B. Hall, 1991, A History of Major Hanford Facilities and Processes Involving 

Radioactive Material, PNL-6964 HEDR, Pacific Northwest Laboratory, Richland, Washington, 

March.

Cleavenger, P. M., and S. P. Gydesen. 1989. Stack Gas Disposal Extracts: March 1947 – January 

1952. HW-89072, Hanford Reading Room Number 8820. October.

Cross, W. G., N. O. Freedman, and P. Y. Young, 1992, “Beta Ray Dose Distributions from Skin 

Contamination,” Radiation Protection Dosimetry, volume 40, number 3, pp. 149–168.

Delong, C. W., 1950, Collection and Analysis of Active Particles, General Electric Company, Hanford 

Works, HW 15802, January 27.

Donelson, R. N., 1953, HW-29346, General Electric Company, Hanford Works, Richland, 

Washington, September 5.

Eckerman, K. F., R. W. Leggett, C. B. Nelson, J. S. Puskin, A. C. B. Richardson, and R.N. Short,

2002, Cancer Risk Coefficients for Environmental Exposure to Radionuclides, CD Supplement 

to Federal Guidance Report No. 13, EPA 402-R-99-001, Rev. 1, U.S. Environmental 

Protection Agency, Office of Radiation and Indoor Air, Washington, D.C., September.

Ebright, D. B., 1954, History of the REDOX Ruthenium Problem, Letter Report to W. A. McAdams, 

HW-32473, General Electric Company, Hanford Atomic Products Operation, Richland, 

Washington, July 16.

Farris, W. T., B. A. Napier, P. W. Eslinger, T. A. Ikenberry, D. B. Shipler, and J. C. Simpson, 1994, 

Atmospheric Pathway Dosimetry Report, 1944-1992, PNWD-2228 HEDR, Battelle, Pacific 

Northwest Laboratories, Pacific Northwest Laboratory, Richland, Washington, October.

Foster, R. F., and I. C. Nelson, 1961. Evaluation of Radiological Conditions in the Vicinity of Hanford 

for 1960. HW-68435. June 1. 
Document No. ORAUT-TKBS-0006-4 Revision No. 02 Effective Date: 06/05/2007 Page 35 of 56

Gerber, M. S., 1992, Legend and Legacy: Fifty Years of Defense Production at the Hanford Site, 

WHC-MR-0293, Revision 2, Westinghouse Hanford Company, Richland, Washington, 

September.

Gerber, M. S., 1993, Manhattan Project Buildings and Facilities at the Hanford Site: A Construction 

History, WCH-MR-0425, Westinghouse Hanford Company, Richland, Washington, September.

Greenfield, H. H., 1954, Additional Pressure Drop Flow Characteristics of K Pile Outlet Tube Fitting 

Assembly, HW-33061, General Electric Company, Hanford Works, Richland, Washington, 

September 14.

Gregg, A. 1948. "Minutes: Advisory Committee for Biology and Medicine, Twelfth Meeting Held at

Hanford Operations Office, Richland, Washington, October 8-9, 1948." Hanford Reading 

Room Number 10727. December 9.

Gross, C. N., 1948, Stack Gas Decontamination, Separations Plants Development of 

Decontamination Systems, HW-9175, General Electric Company, Hanford Works, Richland, 

Washington, March 12.

Groves, L. R., 1962, Now It Can Be Told, The Story of the Manhattan Project, Harper and Brothers, 

New York, New York.

Gydesen, S. P., 1992, Documents Containing Operating Data for Hanford Separations Processes, 

1944-1972, PNWD-2028-HEDR, Battelle, Pacific Northwest Laboratories, Pacific Northwest 

Laboratory, Richland, Washington, September.

Hanf, R. W., and M. E. Thiede, 1994, Environmental Radiological Monitoring of Air, Rain, and Snow 

on and near the Hanford Site, 1945-1957, PNWD-2234 HEDR, Battelle, Pacific Northwest 

Laboratories, Pacific Northwest Laboratory, Richland, Washington, March.

Healy, J. W., 1945, Special Studies Branch Report for Weeks 5/20/1945 through 6/26/1945, Letter 

Report to H. M. Parker, HW-32894, General Electric Company, Hanford Atomic Products 

Operation, Richland, Washington, December 30.

Healy, J. W., 1948, Long Lived Fission Activities in the Stack Gases and Vegetation at the Hanford 

Works, HW-10758, General Electric Company, Hanford Works, August 17.

Healy, J. W., 1955, Preliminary Estimates of Wind Pickup and Impaction of Particles, HW-35542, 

General Electric Company, Hanford Atomic Products Operation, Richland, Washington, March 

1.

Heeb, C. M., 1994, Radionuclide Releases to the Atmosphere from Hanford Operations, 1944-1972, 

PNWD-2222 HEDR, Battelle, Pacific Northwest Laboratories, Pacific Northwest Laboratory, 

Richland, Washington, May.

Heeb, C. M., and S. P. Gydesen, 1994, Sources of Secondary Radionuclide Releases from Hanford 

Operations, PNWD-2254 HEDR, Battelle, Pacific Northwest Laboratories, Pacific Northwest 

Laboratory, Richland, Washington, May.

ICRP (International Commission on Radiological Protection), 1995, Dose Coefficients for Intakes of 

Radionuclides by Workers, Publication 68, Pergamon Press, Oxford, England.
Document No. ORAUT-TKBS-0006-4 Revision No. 02 Effective Date: 06/05/2007 Page 36 of 56

Irish, E. R., 1955, Technical Appraisal of REDOX Ruthenium Problems and their Resolution, HW34882, General Electric Company, Hanford Atomic Products Operation, Richland, 

Washington, January 21.

Johnson, W. E., 1954, Undue Contamination in Construction Areas, letter to D. F. Shaw, (U.S. Atomic 

Energy Commission, Hanford Operations Office), June 8, General Electric Company, Hanford 

Works, Richland, Washington.

Jones, A., P. Mansfield, and K. Bell, 1998, “Implications of Deposition on Skin for Accident 

Consequence Assessments,” Radiological Protection Bulletin No. 207, pp. 9–14.

Junkins, R. L., E. C. Watson, I. C. Nelson, and R. C. Henle, 1960, Evaluation of Radiological 

Conditions in the Vicinity of Hanford for 1959, HW-64371, General Electric Company, Hanford 

Atomic Products Operation, Richland, Washington, May 9.

Mickelson, M. L., 1947, Preliminary Report on Existing Active Particle Hazard-200 Areas, HW-7865, 

General Electric Company, Hanford Works, Richland, Washington, October 22.

Napier, B. A., 2002, “A Re-Evaluation of the 131I Atmospheric Releases from the Hanford Site,” 

Health Physics, volume 83, number 2, pp. 204–226. 

NCRP (National Council on Radiation Protection and Measurements), 1996, Screening Models for 

Releases of Radionuclides to Air, Surface Water, and Ground Water, Report 123, Bethesda, 

Maryland.

Nelson, I. C., editor, 1961, Evaluation of Radiological Conditions in the Vicinity of Hanford for 1960, 

HW-68435, General Electric Company, Hanford Atomic Products Operation, Richland, 

Washington, June 1.

ORAUT (Oak Ridge Associated Universities Team), 2003, Technical Basis Document for the 

Savannah River Site to be used for EEOICPA Dose Reconstructions, ORAUT-TKBS-0003, 

Rev. 00, Oak Ridge, Tennessee, July 15.

ORAUT (Oak Ridge Associated Universities Team), 2006, DOE Technical Basis Document 

Development, Review and Approval Process, ORAUT-PROC-0031, Rev. 01 PC-1, Oak Ridge, 

Tennessee, February 10.

Paas, H. J., 1952, Radioactive Contamination in the Hanford Environs for the Period April, May, June, 

1952, HW-26493, General Electric Company, Hanford Atomic Products Operation, Richland, 

Washington, December 15.

Paas, H. J., 1953a, Radioactive Contamination in the Hanford Environs for the Period January, 

February, March 1953, HW-28009, General Electric Company, Hanford Atomic Products 

Operation, Richland, Washington, May 21.

Paas, H. J., 1953b, Radioactive Contamination in the Hanford Environs from the Period October, 

November, December 1952, HW-27641, General Electric Company, Hanford Works, Richland, 

Washington, April 20.
Document No. ORAUT-TKBS-0006-4 Revision No. 02 Effective Date: 06/05/2007 Page 37 of 56

Paas, H. J., 1954, Radioactive Contamination in the Hanford Environs from the Period April, May, 

June 1954, HW-33896, General Electric Company, Hanford Works, Richland, Washington, 

November 1954.

Parker, H. M., 1947, Actions Taken on the Spot Contamination in the Separations Plant Areas, HW7920, General Electric Company, Hanford Works, Richland, Washington, October 30.

Parker, H. M., 1948a, Progress Report on “Action Taken on the Spot Contamination in the 

Separations Plant Area”, HW-8624, General Electric Company, Hanford Works, Richland, 

Washington, January 20.

Parker, H. M., 1948b, Review of the Stack Discharge Active Contamination Problem, HW-9259, 

General Electric Company, Hanford Atomic Products Operation, Richland, Washington, March 

22.

Parker, H. M., 1954, Status of Ground Contamination Problems, HW-33068, General Electric 

Company, Hanford Works, Richland, Washington, September 15.

Parker, H. M., 1956, Radiation Exposure from Environmental Hazards, in Proceedings of the 

International Conference on the Peaceful Uses of Atomic Energy, Geneva, Switzerland, 8 

August-20 August, 1955, Volume 13, Legal, Administrative, Health and Safety Aspects of 

Large-Scale Use of Nuclear Energy, United Nations, New York, New York, pp. 305–310.

Pilcher, G. E., J. K. Soldat, Z. E. Carey, 1954, Radioactive Contamination in the Hanford Environs for 

the Period July, August, September, 1954, HW-36504, General Electric Company, Hanford 

Atomic Products Operation, Richland, Washington, April 20.

Ramsdell, J. V., Jr., C. A. Simonen, and K. W. Burk, 1994, Regional Atmospheric Transport Code for 

Hanford Emissions Tracking (RATCHET), PNWD-2224 HEDR, Battelle, Pacific Northwest 

Laboratories, Pacific Northwest Laboratory, Richland, Washington, January.

Regional Radiation Measurements Unit, 1955, Radioactive Contamination in the Hanford Environs for 

the Period October, November, and December, 1954, HW-36505, General Electric Company, 

Hanford Atomic Products Operation, Richland, Washington, 1955.

Roberts, R. E., 1958, History of Airborne Contamination and Control - 200 Areas, HW-55569, General 

Electric Company, Hanford Atomic Products Operation, Richland, Washington, April 1.

Singlevich, W., 1948, Radioactive Contamination in the Columbia River and in the Air and Radiation 

Levels Measured in the Air at Hanford Works and Vicinity for 1945, 1946, 1947, and Early 

1948, HW-9871, General Electric Company, Hanford Atomic Products Operation, Richland, 

Washington, May 24.

Singlevich, W., 1949, Radioactive Contamination in the Environs of the Hanford Works for the Period 

July, August, September 1948, HW-12677, General Electric Company, Hanford Atomic 

Products Operation, Richland, Washington, March 10.

Stainken, F. A. R., 1948, Primary Report on the Chronology of the Separations Plant Stack Discharge 

Active Particle Contamination Problem at Hanford Works, HW-11082, General Electric 

Company, Hanford Atomic Products Operation, Richland, Washington, September 15.
Document No. ORAUT-TKBS-0006-4 Revision No. 02 Effective Date: 06/05/2007 Page 38 of 56

Thorburn, R. C., 1948, Radio-active Particle Investigation, HW-10261, General Electric Company, 

Hanford Works, Richland, Washington, June 11. 

Till, J. E., P. G. Voillequé, G. G. Killough, and S. K. Rope, 2002, Methods for Estimating Radiation 

Doses from Short-Lived Gaseous Radionuclides and Radioactive Particles Released to the 

Atmosphere during Early Hanford Operations, RAC Report No. 2-CDC-Task Order 3-2000-

FINAL, U.S. Department of Health and Human Services, Centers for Disease Control and 

Prevention, Atlanta, Georgia, November.

Warren, J. H., 1961, Control of I-131 Releases to Atmosphere, HW-68392, General Electric 

Company, Hanford Atomic Products Operation, Richland, Washington, February 6.

Whicker, F. W., and V. Schultz, 1982, Radioecology: Nuclear Energy and the Environment, Volume 1, 

CRC Press, Boca Raton, Florida.
Document No. ORAUT-TKBS-0006-4 Revision No. 02 Effective Date: 06/05/2007 Page 39 of 56

ATTACHMENT A

Page 1 of 18

LIST OF TABLES

TABLE TITLE

A-1 Source term data for 131I releases........................................................................................

PAGE

40

A-2 Source term data for 41Ar releases ...................................................................................... 41

A-3 Source term data for 144Ce/144Pr particulate releases .......................................................... 43

A-4 Source term data for 137Cs/137mBa particulate releases ........................................................ 44

A-5 Source term data for 239Pu particulate releases................................................................... 45

A-6 Source term data for 103Ru/103mRh particulate releases........................................................ 46

A-7 Source term data for 106Ru/106Rh particulate releases ......................................................... 47

A-8 Source term data for 90Sr/90Y particulate releases ............................................................... 48

A-9 Source term data for 95Zr/95Nb particulate releases ............................................................. 49

A-10 Atmospheric dispersion factors ........................................................................................... 50

A-11 Ar-41 submersion gamma dose (Sv) and skin dose (Sv)..................................................... 53

A-12 Intakes of particulate radionuclides ..................................................................................... 54

A-13 Intakes from 3H from 108-B................................................................................................. 56
Document No. ORAUT-TKBS-0006-4 Revision No. 02 Effective Date: 06/05/2007 Page 40 of 56

ATTACHMENT A

Page 2 of 18

Table A-1. Source term data for 131I releases (Ci/yr). Date T plant T_SD B plant B_SD REDOX R_SD PUREX P_SD

1944 2.10E+03 3.97E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1945 2.60E+05 1.71E+05 2.94E+05 1.98E+05 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1946 2.25E+04 1.59E+04 7.40E+04 4.23E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1947 1.32E+04 8.78E+03 1.88E+04 1.36E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1948 8.76E+02 5.33E+02 9.66E+02 6.20E+02 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1949 8.07E+03 1.36E+04 6.53E+02 3.85E+02 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1950 4.25E+03 3.36E+03 3.18E+03 2.85E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1951 2.22E+04 2.03E+04 1.56E+04 1.37E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1952 2.88E+03 2.44E+03 1.32E+03 1.52E+03 2.85E+03 2.13E+03 0.00E+00 0.00E+00

1953 7.88E+02 5.65E+02 0.00E+00 0.00E+00 1.62E+03 1.08E+03 0.00E+00 0.00E+00

1954 6.42E+02 4.85E+02 0.00E+00 0.00E+00 4.94E+02 3.41E+02 0.00E+00 0.00E+00

1955 2.40E+02 1.68E+02 0.00E+00 0.00E+00 6.94E+02 6.41E+02 0.00E+00 0.00E+00

1956 1.75E-02 3.21E-02 0.00E+00 0.00E+00 1.24E+02 9.78E+01 3.96E+01 3.53E+01

1957 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.77E+02 2.25E+02 1.02E+02 7.50E+01

1958 0.00E+00 0.00E+00 0.00E+00 0.00E+00 6.68E+02 5.00E+02 4.67E+02 3.01E+02

1959 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.49E+00 2.28E+00 3.11E+02 1.85E+02

1960 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.62E+00 4.39E+00 3.11E+02 2.56E+02

1961 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.10E+01 1.34E+01 1.16E+02 6.99E+01

1962 0.00E+00 0.00E+00 0.00E+00 0.00E+00 6.34E+01 6.80E+01 1.09E+02 1.25E+02

1963 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.64E+01 3.48E+01 1.55E+02 1.94E+02

1964 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.60E+01 2.07E+01 8.83E+01 5.93E+01

1965 0.00E+00 0.00E+00 0.00E+00 0.00E+00 5.30E+01 4.71E+01 4.19E+01 3.54E+01

1966 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.67E+00 3.69E+00 5.92E+01 5.06E+01

1967 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.09E+01 3.19E+01

1968 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 7.87E+00 6.64E+00

1969 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.21E+00 2.46E+00

1970 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 6.89E-01 5.26E-01

1971 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.86E-01 1.65E-01

1972 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 5.01E-01 1.11E-10

1973 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1974 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1975 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1976 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1977 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1978 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1979 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1980 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1981 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1982 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1983 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1984 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1985 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.00E-01 2.00E-02

1986 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.00E-01 2.00E-02

1987 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.00E-04 2.00E-05

1988 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.00E-04 4.00E-05

1989 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.70E-02 1.70E-03

1990 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.40E-03 1.40E-04

1991 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1992 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1993 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1994 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1995 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1996 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1997 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1998 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1999 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

2000 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

2001 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
Document No. ORAUT-TKBS-0006-4 Revision No. 02 Effective Date: 06/05/2007 Page 41 of 56

ATTACHMENT A

Page 3 of 18

Table A-2. Source term data for 41Ar releases (Ci/yr). Year B B_SD C C_SD KE KE_SD KW KW_SD

1944 6.69E+03 3.76E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1945 2.68E+04 7.53E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1946 6.69E+03 3.76E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1947 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1948 1.34E+04 5.32E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1949 2.68E+04 7.53E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1950 2.68E+04 7.53E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1951 2.68E+04 7.53E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1952 2.68E+04 7.53E+03 1.40E+04 9.67E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1953 2.68E+04 7.53E+03 8.42E+04 2.37E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1954 2.68E+04 7.53E+03 8.42E+04 2.37E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1955 2.68E+04 7.53E+03 8.42E+04 2.37E+04 6.62E+04 2.15E+04 6.98E+04 2.15E+04

1956 2.23E+04 6.87E+03 8.42E+04 2.37E+04 8.83E+04 2.48E+04 8.38E+04 2.36E+04

1957 2.68E+04 7.53E+03 8.42E+04 2.37E+04 8.83E+04 2.48E+04 8.38E+04 2.36E+04

1958 2.68E+04 7.53E+03 8.42E+04 2.37E+04 8.83E+04 2.48E+04 8.38E+04 2.36E+04

1959 2.68E+04 7.53E+03 8.42E+04 2.37E+04 8.83E+04 2.48E+04 8.38E+04 2.36E+04

1960 2.68E+04 7.53E+03 8.42E+04 2.37E+04 8.83E+04 2.48E+04 8.38E+04 2.36E+04

1961 2.68E+04 7.53E+03 8.42E+04 2.37E+04 8.83E+04 2.48E+04 8.38E+04 2.36E+04

1962 2.68E+04 7.53E+03 8.42E+04 2.37E+04 8.83E+04 2.48E+04 8.38E+04 2.36E+04

1963 2.68E+04 7.53E+03 8.42E+04 2.37E+04 8.83E+04 2.48E+04 8.38E+04 2.36E+04

1964 2.68E+04 7.53E+03 8.42E+04 2.37E+04 8.83E+04 2.48E+04 8.38E+04 2.36E+04

1965 2.68E+04 7.53E+03 8.42E+04 2.37E+04 8.83E+04 2.48E+04 8.38E+04 2.36E+04

1966 2.68E+04 7.53E+03 8.42E+04 2.37E+04 8.83E+04 2.48E+04 8.38E+04 2.36E+04

1967 2.68E+04 7.53E+03 8.42E+04 2.37E+04 8.83E+04 2.48E+04 8.38E+04 2.36E+04

1968 4.46E+03 3.07E+03 8.42E+04 2.37E+04 8.83E+04 2.48E+04 8.38E+04 2.36E+04

1969 0.00E+00 0.00E+00 2.81E+04 1.37E+04 8.83E+04 2.48E+04 8.38E+04 2.36E+04

1970 0.00E+00 0.00E+00 0.00E+00 0.00E+00 8.83E+04 2.48E+04 6.98E+03 6.80E+03

1971 0.00E+00 0.00E+00 0.00E+00 0.00E+00 7.36E+03 7.17E+03 0.00E+00 0.00E+00

1972 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1973 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1974 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1975 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1976 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1977 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1978 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1979 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1980 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1981 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1982 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1983 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1984 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1985 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1986 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1987 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1988 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1989 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1990 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1991 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1992 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1993 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1994 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1995 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1996 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1997 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1998 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1999 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

2000 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

2001 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
Document No. ORAUT-TKBS-0006-4 Revision No. 02 Effective Date: 06/05/2007 Page 42 of 56

ATTACHMENT A

Page 4 of 18

Year N N_SD D D_SD DR DR_SD H H_SD F F_SD

1944 0.00E+00 0.00E+00 2.24E+03 2.18E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1945 0.00E+00 0.00E+00 2.69E+04 7.56E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.45E+04 7.20E+03

1946 0.00E+00 0.00E+00 2.69E+04 7.56E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.68E+04 7.53E+03

1947 0.00E+00 0.00E+00 2.69E+04 7.56E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.68E+04 7.53E+03

1948 0.00E+00 0.00E+00 2.69E+04 7.56E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.68E+04 7.53E+03

1949 0.00E+00 0.00E+00 2.69E+04 7.56E+03 0.00E+00 0.00E+00 2.57E+04 1.45E+04 2.68E+04 7.53E+03

1950 0.00E+00 0.00E+00 2.69E+04 7.56E+03 6.72E+03 3.78E+03 1.03E+05 2.90E+04 2.68E+04 7.53E+03

1951 0.00E+00 0.00E+00 2.69E+04 7.56E+03 2.69E+04 7.56E+03 1.03E+05 2.90E+04 2.68E+04 7.53E+03

1952 0.00E+00 0.00E+00 2.69E+04 7.56E+03 2.69E+04 7.56E+03 1.03E+05 2.90E+04 2.68E+04 7.53E+03

1953 0.00E+00 0.00E+00 2.69E+04 7.56E+03 2.69E+04 7.56E+03 1.03E+05 2.90E+04 2.68E+04 7.53E+03

1954 0.00E+00 0.00E+00 2.69E+04 7.56E+03 2.69E+04 7.56E+03 1.03E+05 2.90E+04 2.68E+04 7.53E+03

1955 0.00E+00 0.00E+00 2.69E+04 7.56E+03 2.69E+04 7.56E+03 1.03E+05 2.90E+04 2.68E+04 7.53E+03

1956 0.00E+00 0.00E+00 2.69E+04 7.56E+03 2.69E+04 7.56E+03 1.03E+05 2.90E+04 2.68E+04 7.53E+03

1957 0.00E+00 0.00E+00 2.46E+04 7.24E+03 2.69E+04 7.56E+03 9.44E+04 2.77E+04 2.68E+04 7.53E+03

1958 0.00E+00 0.00E+00 2.69E+04 7.56E+03 2.69E+04 7.56E+03 1.03E+05 2.90E+04 2.68E+04 7.53E+03

1959 0.00E+00 0.00E+00 2.69E+04 7.56E+03 2.69E+04 7.56E+03 1.03E+05 2.90E+04 2.68E+04 7.53E+03

1960 0.00E+00 0.00E+00 2.69E+04 7.56E+03 2.69E+04 7.56E+03 1.03E+05 2.90E+04 2.68E+04 7.53E+03

1961 0.00E+00 0.00E+00 2.69E+04 7.56E+03 2.69E+04 7.56E+03 1.03E+05 2.90E+04 2.68E+04 7.53E+03

1962 0.00E+00 0.00E+00 2.69E+04 7.56E+03 2.69E+04 7.56E+03 1.03E+05 2.90E+04 2.68E+04 7.53E+03

1963 0.00E+00 0.00E+00 2.69E+04 7.56E+03 2.69E+04 7.56E+03 1.03E+05 2.90E+04 2.68E+04 7.53E+03

1964 1.30E+05 1.30E+04 2.69E+04 7.56E+03 2.69E+04 7.56E+03 1.03E+05 2.90E+04 2.68E+04 7.53E+03

1965 1.30E+05 1.30E+04 2.69E+04 7.56E+03 0.00E+00 0.00E+00 3.43E+04 1.67E+04 1.34E+04 5.32E+03

1966 1.30E+05 1.30E+04 2.69E+04 7.56E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1967 1.30E+05 1.30E+04 1.34E+04 5.35E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1968 1.30E+05 1.30E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1969 1.30E+05 1.30E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1970 1.30E+05 1.30E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1971 1.30E+05 1.30E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1972 1.00E+05 1.00E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1973 1.00E+05 1.00E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1974 5.00E+04 5.00E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1975 3.09E+04 3.09E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1976 3.54E+04 3.54E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1977 1.31E+05 1.31E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1978 1.10E+05 1.10E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1979 8.60E+04 8.60E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1980 2.30E+04 2.30E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1981 6.50E+04 6.50E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1982 1.14E+05 1.14E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1983 1.21E+05 1.21E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1984 7.70E+04 7.70E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1985 6.90E+04 6.90E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1986 1.20E+05 1.20E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1987 4.50E+03 4.50E+02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1988 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1989 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1990 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1991 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1992 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1993 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1994 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1995 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1996 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1997 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1998 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1999 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

2000 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

2001 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
Document No. ORAUT-TKBS-0006-4 Revision No. 02 Effective Date: 06/05/2007 Page 43 of 56

ATTACHMENT A

Page 5 of 18

Table A-3. Source term data for 144Ce/144Pr particulate releases (Ci/yr).

Date T T_SD B B_SD REDOX R_SD PUREX P_SD

1944 6.60E-01 5.72E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1945 1.00E+02 3.11E+01 9.28E+01 2.99E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1946 9.85E+01 2.81E+01 1.75E+02 4.44E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1947 8.85E+01 2.24E+01 1.01E+02 2.56E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1948 2.95E+01 1.26E+01 3.46E+01 1.49E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1949 9.19E-01 2.41E-01 8.22E-01 2.21E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1950 1.41E+00 3.64E-01 1.54E+00 4.02E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1951 2.50E+00 6.33E-01 2.31E+00 6.00E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1952 1.59E+00 4.67E-01 6.40E-01 2.97E-01 4.38E+00 1.21E+00 0.00E+00 0.00E+00

1953 1.19E+00 3.20E-01 0.00E+00 0.00E+00 1.75E+01 9.70E+00 0.00E+00 0.00E+00

1954 2.61E+00 6.78E-01 0.00E+00 0.00E+00 8.92E+00 2.39E+00 0.00E+00 0.00E+00

1955 3.03E+00 8.06E-01 0.00E+00 0.00E+00 9.23E+00 2.52E+00 0.00E+00 0.00E+00

1956 1.00E-01 6.20E-02 0.00E+00 0.00E+00 8.66E+00 2.43E+00 1.21E+01 3.57E+00

1957 0.00E+00 0.00E+00 0.00E+00 0.00E+00 9.93E+00 2.58E+00 2.40E+01 6.06E+00

1958 0.00E+00 0.00E+00 0.00E+00 0.00E+00 7.66E+00 2.18E+00 2.94E+01 7.83E+00

1959 0.00E+00 0.00E+00 0.00E+00 0.00E+00 5.35E+00 1.39E+00 3.59E+01 9.31E+00

1960 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.59E+00 1.30E+00 4.14E+01 1.11E+01

1961 0.00E+00 0.00E+00 0.00E+00 0.00E+00 8.23E+00 2.17E+00 4.05E+01 1.06E+01

1962 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.36E+01 6.84E+00 1.27E+02 3.42E+01

1963 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.72E+01 8.10E+00 1.13E+02 3.36E+01

1964 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.52E+01 1.01E+01 1.26E+02 3.66E+01

1965 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.75E+01 1.09E+01 1.17E+02 3.28E+01

1966 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.97E+01 1.90E+01 7.82E+01 2.67E+01

1967 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.07E+02 2.87E+01

1968 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.03E+02 2.79E+01

1969 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 7.28E+01 1.94E+01

1970 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.72E+01 8.25E+00

1971 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.03E+01 1.12E+01

1972 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.55E+00 2.53E+00

1973 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1974 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1975 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1976 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1977 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1978 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1979 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1980 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1981 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1982 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1983 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1984 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.00E-01 1.00E-02

1985 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.00E-01 1.00E-02

1986 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1987 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1988 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.00E-04 1.00E-05

1989 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1990 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1991 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1992 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1993 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1994 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1995 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1996 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1997 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1998 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1999 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

2000 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

2001 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
Document No. ORAUT-TKBS-0006-4 Revision No. 02 Effective Date: 06/05/2007 Page 44 of 56

ATTACHMENT A

Page 6 of 18

Table A-4. Source term data for 137Cs/137mBa particulate releases (Ci/yr).

Date T T_SD B B_SD REDOX R_SD PUREX P_SD

1944 1.90E-02 1.65E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1945 3.38E+00 1.07E+00 3.12E+00 1.01E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1946 3.74E+00 1.09E+00 6.14E+00 1.56E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1947 3.26E+00 8.23E-01 3.68E+00 9.33E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1948 1.16E+00 4.94E-01 1.36E+00 5.83E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1949 3.86E-02 1.01E-02 3.11E-02 8.62E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1950 5.94E-02 1.54E-02 6.49E-02 1.68E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1951 9.19E-02 2.33E-02 8.65E-02 2.25E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1952 5.92E-02 1.71E-02 2.37E-02 1.10E-02 1.71E-01 4.71E-02 0.00E+00 0.00E+00

1953 4.41E-02 1.21E-02 0.00E+00 0.00E+00 2.87E-01 7.80E-02 0.00E+00 0.00E+00

1954 8.60E-02 2.22E-02 0.00E+00 0.00E+00 3.41E-01 9.17E-02 0.00E+00 0.00E+00

1955 1.05E-01 2.80E-02 0.00E+00 0.00E+00 3.93E-01 1.14E-01 0.00E+00 0.00E+00

1956 4.20E-03 2.62E-03 0.00E+00 0.00E+00 3.23E-01 9.22E-02 4.62E-01 1.38E-01

1957 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.54E-01 9.13E-02 8.57E-01 2.16E-01

1958 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.70E-01 7.59E-02 9.88E-01 2.64E-01

1959 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.38E-01 6.16E-02 1.23E+00 3.18E-01

1960 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.96E-01 5.51E-02 1.44E+00 3.85E-01

1961 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.47E-01 9.11E-02 1.40E+00 3.71E-01

1962 0.00E+00 0.00E+00 0.00E+00 0.00E+00 8.67E-02 2.47E-02 5.34E-01 1.44E-01

1963 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.02E-01 3.06E-02 4.89E-01 1.40E-01

1964 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.64E-01 4.68E-02 5.02E-01 1.45E-01

1965 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.37E-01 4.02E-02 5.24E-01 1.49E-01

1966 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.25E-01 4.30E-02 3.66E-01 1.22E-01

1967 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.29E-01 1.17E-01

1968 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.69E-01 9.96E-02

1969 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.69E-01 7.37E-02

1970 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 6.24E-02 3.05E-02

1971 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.76E-01 9.73E-02

1972 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 5.32E-02 3.67E-02

1973 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1974 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1975 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1976 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1977 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1978 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1979 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1980 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1981 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1982 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1983 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.90E-02 2.90E-03

1984 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.00E-02 4.00E-03

1985 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.00E-02 1.00E-03

1986 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 8.70E-03 8.70E-04

1987 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.00E-05 4.00E-06

1988 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 8.00E-04 8.00E-05

1989 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.30E-03 1.30E-04

1990 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 6.90E-04 6.90E-05

1991 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.10E-03 4.10E-04

1992 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.30E-02 2.30E-03

1993 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.80E-02 1.80E-03

1994 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 6.60E-04 6.60E-05

1995 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 6.50E-04 6.50E-05

1996 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 6.00E-04 6.00E-05

1997 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 9.60E-04 9.60E-05

1998 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.20E-04 2.20E-05

1999 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 8.50E-05 8.50E-06

2000 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.80E-04 1.80E-05

2001 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.50E-04 1.50E-05
Document No. ORAUT-TKBS-0006-4 Revision No. 02 Effective Date: 06/05/2007 Page 45 of 56

ATTACHMENT A

Page 7 of 18

Table A-5. Source term data for 239Pu particulate releases (Ci/yr). Date T T_SD B B_SD REDOX R_SD PUREX P_SD Z Z_SD

1944 6.50E-04 1.26E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1945 1.09E-01 7.66E-01 1.01E-01 7.29E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1946 1.18E-01 7.56E-01 1.98E-01 1.12E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1947 1.05E-01 5.91E-01 1.20E-01 6.79E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1948 3.76E-02 3.57E-01 4.38E-02 4.19E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1949 1.22E-03 7.15E-03 1.12E-03 6.73E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.45E-03 8.53E-03

1950 1.83E-03 1.06E-02 2.01E-03 1.16E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.25E-03 1.30E-02

1951 2.78E-03 1.57E-02 2.59E-03 1.50E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.23E-03 1.83E-02

1952 1.76E-03 1.14E-02 7.09E-04 7.29E-03 5.03E-03 3.10E-02 0.00E+00 0.00E+00 4.53E-03 2.58E-02

1953 1.28E-03 7.78E-03 0.00E+00 0.00E+00 8.55E-03 5.20E-02 0.00E+00 0.00E+00 6.17E-03 3.53E-02

1954 2.75E-03 1.60E-02 0.00E+00 0.00E+00 9.90E-03 5.94E-02 0.00E+00 0.00E+00 7.10E-03 4.28E-02

1955 3.38E-03 2.00E-02 0.00E+00 0.00E+00 1.17E-02 7.44E-02 0.00E+00 0.00E+00 9.45E-03 5.68E-02

1956 1.35E-04 1.89E-03 0.00E+00 0.00E+00 9.76E-03 6.10E-02 1.35E-02 8.87E-02 1.34E-02 7.93E-02

1957 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.05E-02 6.06E-02 2.56E-02 1.44E-01 2.20E-02 1.24E-01

1958 0.00E+00 0.00E+00 0.00E+00 0.00E+00 7.85E-03 4.98E-02 2.95E-02 1.76E-01 2.34E-02 1.35E-01

1959 0.00E+00 0.00E+00 0.00E+00 0.00E+00 5.78E-03 3.40E-02 3.53E-02 2.04E-01 2.56E-02 1.46E-01

1960 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.80E-03 3.09E-02 4.19E-02 2.50E-01 2.85E-02 1.67E-01

1961 0.00E+00 0.00E+00 0.00E+00 0.00E+00 7.92E-03 4.65E-02 4.14E-02 2.42E-01 3.26E-02 1.86E-01

1962 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.65E-02 1.83E-01 5.28E-04 3.16E-03 1.52E-02 1.38E-01

1963 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.03E-02 6.83E-02 4.63E-04 3.08E-03 7.05E-03 4.49E-02

1964 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.40E-02 8.91E-02 1.02E-03 1.15E-02 7.68E-03 4.98E-02

1965 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.01E-02 2.96E-01 5.33E-04 3.30E-03 1.77E-02 1.76E-01

1966 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.75E-02 1.47E-01 3.29E-04 2.47E-03 1.50E-02 1.23E-01

1967 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 5.09E-04 3.09E-03 7.57E-04 9.31E-03

1968 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 5.08E-04 3.00E-03 3.25E-04 1.93E-03

1969 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.95E-04 2.37E-03 2.47E-04 1.49E-03

1970 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 9.24E-05 9.90E-04 1.08E-04 9.27E-04

1971 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.52E-04 2.05E-03 1.61E-04 1.30E-03

1972 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.19E-05 5.07E-04 2.03E-05 3.23E-04

1973 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1974 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1975 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1976 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1977 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1978 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1979 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1980 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1981 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1982 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1983 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 6.20E-04 6.20E-05 0.00E+00 0.00E+00

1984 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 7.40E-03 7.40E-04 0.00E+00 0.00E+00

1985 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.00E-02 1.00E-03 0.00E+00 0.00E+00

1986 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.00E-03 3.00E-04 0.00E+00 0.00E+00

1987 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.00E-04 4.00E-05 0.00E+00 0.00E+00

1988 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.00E-04 2.00E-05 0.00E+00 0.00E+00

1989 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 8.20E-04 8.20E-05

1990 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.00E-04 3.00E-05

1991 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.40E-04 4.40E-05

1992 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.70E-04 4.70E-05

1993 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 5.60E-04 5.60E-05

1994 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.20E-04 4.20E-05

1995 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.20E-04 1.20E-05

1996 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.40E-04 2.40E-05

1997 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.20E-04 1.20E-05

1998 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.00E-04 2.00E-05

1999 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.10E-04 2.10E-05

2000 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 5.10E-04 5.10E-05

2001 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.50E-04 1.50E-05
Document No. ORAUT-TKBS-0006-4 Revision No. 02 Effective Date: 06/05/2007 Page 46 of 56

ATTACHMENT A

Page 8 of 18

Table A-6. Source term data for 103Ru/103mRh particulate releases (Ci/yr). Date T T_SD B B_SD REDOX R_SD PUREX P_SD

1944 9.70E-01 1.14E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1945 8.69E+01 3.51E+01 8.65E+01 3.70E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1946 5.56E+01 2.19E+01 1.17E+02 4.01E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1947 4.69E+01 1.64E+01 5.45E+01 1.93E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1948 1.02E+01 5.88E+00 1.18E+01 6.90E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1949 3.07E-01 1.11E-01 2.63E-01 9.65E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1950 5.27E-01 1.92E-01 5.61E-01 2.05E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1951 1.67E+00 5.75E-01 1.50E+00 5.32E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1952 1.02E+00 4.36E-01 4.37E-01 2.82E-01 4.02E+01 2.68E+01 0.00E+00 0.00E+00

1953 7.19E-01 2.57E-01 0.00E+00 0.00E+00 4.72E+02 5.15E+02 0.00E+00 0.00E+00

1954 1.82E+00 6.53E-01 0.00E+00 0.00E+00 1.14E+03 1.29E+03 0.00E+00 0.00E+00

1955 1.74E+00 6.61E-01 0.00E+00 0.00E+00 2.68E+01 1.02E+01 0.00E+00 0.00E+00

1956 1.70E-02 1.43E-02 0.00E+00 0.00E+00 2.25E+01 8.36E+00 4.25E+00 1.72E+00

1957 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.18E+01 1.15E+01 1.07E+01 3.74E+00

1958 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.15E+01 1.28E+01 1.31E+01 5.37E+00

1959 0.00E+00 0.00E+00 0.00E+00 0.00E+00 5.28E+00 2.21E+00 1.95E+01 6.85E+00

1960 0.00E+00 0.00E+00 0.00E+00 0.00E+00 6.40E+00 2.72E+00 2.12E+01 8.01E+00

1961 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.18E+01 4.97E+00 1.85E+01 6.52E+00

1962 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.07E+00 5.33E-01 8.05E+00 3.09E+00

1963 0.00E+00 0.00E+00 0.00E+00 0.00E+00 7.49E-01 3.69E-01 6.79E+00 2.74E+00

1964 0.00E+00 0.00E+00 0.00E+00 0.00E+00 6.90E-01 2.93E-01 8.57E+00 3.49E+00

1965 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.43E+00 5.96E-01 6.41E+00 2.44E+00

1966 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.33E+00 7.01E-01 4.08E+00 2.19E+00

1967 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.82E+00 1.62E+00

1968 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.97E+00 8.26E-01

1969 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 7.31E-01 2.99E-01

1970 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.95E-01 1.75E-01

1971 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.12E-01 1.05E-01

1972 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.85E-03 4.61E-03

1973 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1974 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1975 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1976 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1977 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1978 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1979 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1980 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1981 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1982 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1983 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1984 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 5.00E-04 5.00E-05

1985 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 5.20E-01 5.20E-02

1986 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.00E-02 2.00E-03

1987 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.00E-04 2.00E-05

1988 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 5.00E-04 5.00E-05

1989 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1990 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1991 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1992 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1993 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1994 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1995 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1996 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1997 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1998 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1999 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

2000 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

2001 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
Document No. ORAUT-TKBS-0006-4 Revision No. 02 Effective Date: 06/05/2007 Page 47 of 56

ATTACHMENT A

Page 9 of 18

Table A-7. Source term data for 106Ru/106Rh particulate releases (Ci/yr). Date T T_SD B B_SD REDOX R_SD PUREX P_SD

1944 6.30E-02 7.37E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1945 1.11E+01 4.73E+00 1.03E+01 4.53E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1946 1.20E+01 4.79E+00 1.94E+01 6.65E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1947 9.99E+00 3.41E+00 1.14E+01 3.91E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1948 3.38E+00 1.95E+00 3.96E+00 2.30E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1949 1.16E-01 4.11E-02 1.06E-01 3.85E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1950 1.98E-01 6.95E-02 2.15E-01 7.56E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1951 3.57E-01 1.23E-01 3.34E-01 1.18E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1952 2.43E-01 9.59E-02 9.79E-02 6.10E-02 1.52E+01 9.12E+00 0.00E+00 0.00E+00

1953 1.72E-01 6.40E-02 0.00E+00 0.00E+00 1.71E+02 1.76E+02 0.00E+00 0.00E+00

1954 3.06E-01 1.07E-01 0.00E+00 0.00E+00 3.53E+02 3.53E+02 0.00E+00 0.00E+00

1955 3.42E-01 1.23E-01 0.00E+00 0.00E+00 1.02E+01 4.06E+00 0.00E+00 0.00E+00

1956 1.23E-02 1.03E-02 0.00E+00 0.00E+00 8.70E+00 3.55E+00 1.84E+00 7.72E-01

1957 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.03E+01 3.59E+00 3.48E+00 1.19E+00

1958 0.00E+00 0.00E+00 0.00E+00 0.00E+00 7.79E+00 3.00E+00 4.15E+00 1.50E+00

1959 0.00E+00 0.00E+00 0.00E+00 0.00E+00 5.44E+00 1.94E+00 5.51E+00 1.94E+00

1960 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.56E+00 1.78E+00 6.30E+00 2.29E+00

1961 0.00E+00 0.00E+00 0.00E+00 0.00E+00 7.83E+00 2.79E+00 6.25E+00 2.21E+00

1962 0.00E+00 0.00E+00 0.00E+00 0.00E+00 7.48E-01 2.91E-01 4.65E+00 1.68E+00

1963 0.00E+00 0.00E+00 0.00E+00 0.00E+00 9.02E-01 3.60E-01 4.20E+00 1.71E+00

1964 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.12E+00 4.37E-01 4.65E+00 1.84E+00

1965 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.22E+00 4.78E-01 4.18E+00 1.59E+00

1966 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.10E+00 1.18E+00 2.65E+00 1.23E+00

1967 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.35E+00 1.58E+00

1968 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.78E+00 1.75E+00

1969 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.61E+00 1.29E+00

1970 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 8.87E-01 5.72E-01

1971 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.14E+00 5.71E-01

1972 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.17E-01 1.14E-01

1973 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1974 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1975 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1976 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1977 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1978 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1979 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1980 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1981 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1982 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1983 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1984 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.00E-01 2.00E-02

1985 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 6.00E-01 6.00E-02

1986 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.00E-01 4.00E-02

1987 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.00E-02 2.00E-03

1988 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.80E-01 1.80E-02

1989 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.20E-02 2.20E-03

1990 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.80E-03 2.80E-04

1991 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.90E-03 2.90E-04

1992 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1993 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.00E-06 4.00E-07

1994 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1995 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.80E-05 1.80E-06

1996 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1997 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1998 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1999 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

2000 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

2001 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
Document No. ORAUT-TKBS-0006-4 Revision No. 02 Effective Date: 06/05/2007 Page 48 of 56

ATTACHMENT A

Page 10 of 18

Table A-8. Source term data for 90Sr/90Y particulate releases (Ci/yr).

Date T T_SD B B_SD REDOX R_SD PUREX P_SD

1944 2.20E-02 1.91E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1945 3.84E+00 1.21E+00 3.55E+00 1.15E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1946 4.26E+00 1.24E+00 6.97E+00 1.77E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1947 3.70E+00 9.35E-01 4.19E+00 1.06E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1948 1.32E+00 5.64E-01 1.55E+00 6.66E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1949 4.36E-02 1.15E-02 3.54E-02 9.82E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1950 6.77E-02 1.75E-02 7.37E-02 1.91E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1951 1.06E-01 2.68E-02 9.79E-02 2.54E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1952 6.78E-02 1.97E-02 2.71E-02 1.25E-02 1.96E-01 5.42E-02 0.00E+00 0.00E+00

1953 5.01E-02 1.38E-02 0.00E+00 0.00E+00 3.26E-01 8.85E-02 0.00E+00 0.00E+00

1954 9.79E-02 2.53E-02 0.00E+00 0.00E+00 3.90E-01 1.05E-01 0.00E+00 0.00E+00

1955 1.21E-01 3.20E-02 0.00E+00 0.00E+00 4.48E-01 1.30E-01 0.00E+00 0.00E+00

1956 4.80E-03 3.00E-03 0.00E+00 0.00E+00 3.65E-01 1.04E-01 5.25E-01 1.57E-01

1957 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.04E-01 1.04E-01 9.75E-01 2.46E-01

1958 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.08E-01 8.65E-02 1.13E+00 3.01E-01

1959 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.69E-01 6.95E-02 1.39E+00 3.61E-01

1960 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.23E-01 6.27E-02 1.64E+00 4.40E-01

1961 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.96E-01 1.04E-01 1.59E+00 4.18E-01

1962 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.35E-01 1.24E-01 2.16E+00 5.78E-01

1963 0.00E+00 0.00E+00 0.00E+00 0.00E+00 5.50E-01 1.63E-01 1.92E+00 5.73E-01

1964 0.00E+00 0.00E+00 0.00E+00 0.00E+00 7.32E-01 2.09E-01 2.11E+00 6.17E-01

1965 0.00E+00 0.00E+00 0.00E+00 0.00E+00 6.99E-01 2.03E-01 2.02E+00 5.69E-01

1966 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.04E+00 4.08E-01 1.41E+00 4.73E-01

1967 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.12E+00 5.70E-01

1968 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.18E+00 5.79E-01

1969 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.74E+00 4.64E-01

1970 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.16E-01 1.99E-01

1971 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.09E+00 4.06E-01

1972 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.08E-01 7.73E-02

1973 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1974 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1975 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1976 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1977 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1978 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1979 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1980 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1981 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1982 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1983 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.00E-03 3.00E-04

1984 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.30E-02 2.30E-03

1985 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 8.50E-03 8.50E-04

1986 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.10E-04 2.10E-05

1987 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.00E-04 2.00E-05

1988 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.00E-04 1.00E-05

1989 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.60E-03 4.60E-04

1990 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 5.30E-03 5.30E-04

1991 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.40E-03 2.40E-04

1992 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.40E-04 4.40E-05

1993 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.70E-04 3.70E-05

1994 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.00E-04 2.00E-05

1995 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.50E-04 2.50E-05

1996 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.50E-04 4.50E-05

1997 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 5.90E-04 5.90E-05

1998 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.70E-04 3.70E-05

1999 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.20E-04 4.20E-05

2000 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.30E-04 3.30E-05

2001 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.90E-04 2.90E-05
Document No. ORAUT-TKBS-0006-4 Revision No. 02 Effective Date: 06/05/2007 Page 49 of 56

ATTACHMENT A

Page 11 of 18

Table A-9. Source term data for 95Zr/95Nb particulate releases (Ci/yr).

Date T T_SD B B_SD REDOX R_SD PUREX P_SD

1944 2.35E+00 8.08E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1945 1.91E+02 2.23E+02 1.83E+02 2.30E+02 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1946 1.35E+02 1.52E+02 2.82E+02 2.83E+02 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1947 1.44E+02 1.45E+02 1.68E+02 1.68E+02 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1948 6.24E+01 8.57E+01 1.12E+02 1.22E+02 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1949 9.07E-01 9.69E-01 1.34E+01 2.39E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1950 1.91E-01 6.58E-01 1.30E-01 4.48E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1951 2.00E+00 2.02E+00 1.79E+00 1.84E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1952 1.02E+00 1.24E+00 4.31E-01 8.05E-01 2.46E+00 2.66E+00 0.00E+00 0.00E+00

1953 7.17E-01 7.51E-01 0.00E+00 0.00E+00 3.81E+00 4.12E+00 0.00E+00 0.00E+00

1954 2.39E+00 2.62E+00 0.00E+00 0.00E+00 3.20E+00 3.41E+00 0.00E+00 0.00E+00

1955 2.46E+00 2.73E+00 0.00E+00 0.00E+00 4.44E+00 5.02E+00 0.00E+00 0.00E+00

1956 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.75E+00 3.95E+00 4.29E+00 4.85E+00

1957 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.44E+00 3.68E+00 8.22E+00 8.42E+00

1958 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.88E+00 3.40E+00 1.14E+01 1.20E+01

1959 0.00E+00 0.00E+00 0.00E+00 0.00E+00 7.11E-01 7.93E-01 1.06E+01 1.09E+01

1960 0.00E+00 0.00E+00 0.00E+00 0.00E+00 7.69E-01 9.05E-01 1.15E+01 1.25E+01

1961 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.21E+00 1.36E+00 1.03E+01 1.06E+01

1962 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.02E+00 1.32E+00 7.47E+00 8.22E+00

1963 0.00E+00 0.00E+00 0.00E+00 0.00E+00 8.24E-01 1.08E+00 6.72E+00 7.68E+00

1964 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.02E+00 1.19E+00 7.34E+00 8.67E+00

1965 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.46E+00 1.74E+00 6.40E+00 7.13E+00

1966 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.14E+00 1.67E+00 2.20E+00 4.10E+00

1967 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.45E+00 4.43E+00

1968 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.27E+00 2.68E+00

1969 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.05E+00 1.21E+00

1970 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.77E-01 6.58E-01

1971 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.11E-01 7.51E-01

1972 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.32E-02 1.18E-01

1973 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1974 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1975 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1976 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1977 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1978 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1979 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1980 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1981 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1982 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1983 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1984 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1985 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1986 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1987 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1988 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1989 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1990 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1991 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1992 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1993 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1994 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1995 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1996 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1997 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1998 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

1999 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

2000 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

2001 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
Document No. ORAUT-TKBS-0006-4 Revision No. 02 Effective Date: 06/05/2007 Page 50 of 56

ATTACHMENT A

Page 12 of 18

In this table, numerical identifiers are used as row and column headings. The row headings are the 

38 receptor locations described in Table 4-6. The column headings represent the combination of 

source location and emission type as:

Table A-10. Atmospheric dispersion 

factors [Bq-(s/m3

) per Bq released].

1 T Plant particles

2 B Plant particles

3 REDOX Plant particles

4 PUREX Plant particles

5 Z Plant particles

6 T Plant iodine

7 B Plant iodine

8 REDOX Plant iodine

9 PUREX Plant iodine

10 B & C Reactors noble gas

11 KE & KW Reactors noble gas

12 N Reactor noble gas

13 D & DR Reactors noble gas

14 H Reactor noble gas

15 F Reactor noble gas
Document No. ORAUT-TKBS-0006-4 Revision No. 02 Effective Date: 06/05/2007 Page 51 of 45

ATTACHMENT A

Page 13 of 18

Node Averages 1

23456789 10 11 12 13 14 15

1 1.17E-07 1.80E-08 3.03E-08 1.44E-08 5.74E-08 1.18E-07 1.84E-08 3.07E-08 1.47E-08 1.53E-08 1.07E-08 7.17E-09 5.86E-09 4.65E-09 4.92E-09

2 2.46E-08 1.35E-07 1.80E-08 5.86E-08 2.03E-08 2.49E-08 1.35E-07 1.84E-08 5.91E-08 1.77E-08 1.17E-08 8.38E-09 6.99E-09 5.87E-09 6.52E-09

3 5.40E-08 1.36E-08 2.92E-07 1.17E-08 2.27E-07 5.46E-08 1.39E-08 2.93E-07 1.20E-08 1.26E-08 8.66E-09 5.78E-09 4.76E-09 3.81E-09 4.05E-09

4 2.35E-08 8.34E-08 1.82E-08 1.20E-07 1.99E-08 2.39E-08 8.39E-08 1.86E-08 1.20E-07 1.72E-08 1.13E-08 7.99E-09 6.90E-09 6.05E-09 6.92E-09

5 6.81E-08 1.46E-08 6.51E-08 1.20E-08 1.94E-07 6.86E-08 1.49E-08 6.55E-08 1.23E-08 1.40E-08 9.21E-09 6.28E-09 5.09E-09 4.11E-09 4.32E-09

6 1.42E-08 1.29E-08 1.04E-08 1.13E-08 1.13E-08 1.45E-08 1.33E-08 1.08E-08 1.17E-08 3.80E-07 1.84E-08 1.10E-08 8.84E-09 6.89E-09 7.04E-09

7 1.62E-08 1.77E-08 1.32E-08 1.75E-08 1.43E-08 1.66E-08 1.82E-08 1.36E-08 1.79E-08 3.13E-08 3.59E-07 2.64E-08 1.79E-08 1.24E-08 1.24E-08

8 1.67E-08 1.95E-08 1.46E-08 1.98E-08 1.51E-08 1.73E-08 2.01E-08 1.52E-08 2.03E-08 2.15E-08 2.64E-08 1.86E-07 4.92E-08 2.22E-08 2.21E-08

9 1.36E-08 1.56E-08 1.20E-08 1.56E-08 1.24E-08 1.41E-08 1.61E-08 1.25E-08 1.61E-08 1.74E-08 2.11E-08 4.43E-08 1.22E-07 3.08E-08 2.67E-08

10 1.21E-08 1.40E-08 1.07E-08 1.38E-08 1.11E-08 1.26E-08 1.44E-08 1.12E-08 1.42E-08 1.63E-08 2.12E-08 3.35E-08 4.88E-08 1.08E-07 3.46E-08

11 1.48E-08 1.67E-08 1.32E-08 1.63E-08 1.37E-08 1.53E-08 1.72E-08 1.37E-08 1.67E-08 1.97E-08 2.87E-08 4.02E-08 3.57E-08 2.63E-08 2.44E-07

12 2.13E-08 1.74E-08 1.44E-08 1.43E-08 1.66E-08 2.17E-08 1.77E-08 1.48E-08 1.46E-08 3.55E-08 1.79E-08 1.11E-08 8.63E-09 6.52E-09 6.96E-09

13 7.65E-09 6.78E-09 6.46E-09 6.24E-09 7.06E-09 7.89E-09 7.01E-09 6.68E-09 6.45E-09 1.76E-08 9.68E-09 6.50E-09 5.19E-09 3.98E-09 4.19E-09

14 1.13E-08 1.33E-08 9.64E-09 1.32E-08 1.02E-08 1.18E-08 1.37E-08 1.01E-08 1.36E-08 1.58E-08 1.97E-08 3.06E-08 2.84E-08 1.95E-08 1.71E-08

15 8.06E-09 9.34E-09 7.24E-09 9.20E-09 7.46E-09 8.40E-09 9.70E-09 7.58E-09 9.53E-09 1.15E-08 1.43E-08 2.08E-08 2.50E-08 3.54E-08 2.04E-08

16 9.18E-09 1.04E-08 8.05E-09 1.02E-08 8.43E-09 9.53E-09 1.07E-08 8.40E-09 1.05E-08 1.35E-08 1.93E-08 2.77E-08 3.37E-08 4.98E-08 2.50E-08

17 8.62E-09 5.76E-09 8.99E-09 5.22E-09 1.00E-08 8.84E-09 5.94E-09 9.21E-09 5.40E-09 9.76E-09 5.48E-09 3.99E-09 3.28E-09 2.60E-09 2.81E-09

18 1.44E-08 1.12E-08 1.82E-08 1.12E-08 1.62E-08 1.48E-08 1.15E-08 1.86E-08 1.15E-08 7.44E-09 5.60E-09 4.23E-09 3.88E-09 3.84E-09 4.72E-09

19 1.83E-08 2.22E-08 1.73E-08 2.32E-08 1.67E-08 1.88E-08 2.25E-08 1.77E-08 2.36E-08 1.32E-08 1.00E-08 7.18E-09 6.52E-09 6.39E-09 7.66E-09

20 6.87E-08 3.41E-08 2.89E-08 2.23E-08 3.33E-08 6.92E-08 3.46E-08 2.92E-08 2.27E-08 1.43E-08 1.01E-08 7.13E-09 5.95E-09 4.85E-09 5.27E-09

21 1.68E-08 1.81E-08 1.43E-08 1.89E-08 1.52E-08 1.73E-08 1.86E-08 1.48E-08 1.94E-08 2.67E-08 7.34E-08 2.82E-08 2.09E-08 1.42E-08 1.46E-08

22 5.53E-08 2.60E-08 2.66E-08 1.88E-08 3.16E-08 5.57E-08 2.65E-08 2.70E-08 1.92E-08 1.54E-08 1.09E-08 7.59E-09 6.22E-09 5.04E-09 5.39E-09

23 1.18E-08 8.79E-09 1.64E-08 8.79E-09 1.43E-08 1.21E-08 9.07E-09 1.68E-08 9.05E-09 6.01E-09 4.53E-09 3.49E-09 3.18E-09 3.13E-09 3.84E-09

24 8.96E-09 1.04E-08 9.14E-09 1.07E-08 8.78E-09 9.27E-09 1.08E-08 9.46E-09 1.11E-08 8.02E-09 7.46E-09 5.79E-09 5.44E-09 5.52E-09 7.13E-09

25 8.35E-09 1.01E-08 8.37E-09 1.06E-08 8.08E-09 8.64E-09 1.04E-08 8.67E-09 1.09E-08 8.23E-09 8.08E-09 6.47E-09 6.16E-09 6.33E-09 8.05E-09

26 1.01E-08 1.07E-08 1.08E-08 1.11E-08 1.01E-08 1.04E-08 1.10E-08 1.11E-08 1.14E-08 7.66E-09 6.43E-09 4.76E-09 4.35E-09 4.33E-09 5.65E-09

27 4.83E-093.71E-09 6.09E-09 3.63E-09 5.70E-09 5.02E-09 3.85E-09 6.30E-09 3.77E-09 3.10E-09 2.45E-09 2.00E-09 1.82E-09 1.72E-09 1.97E-09

28 1.22E-08 1.45E-08 1.15E-08 1.49E-08 1.16E-08 1.26E-08 1.49E-08 1.19E-08 1.53E-08 1.46E-08 2.18E-08 1.91E-08 1.56E-08 1.33E-082.06E-08

29 2.59E-08 2.42E-08 2.72E-08 2.44E-08 2.59E-08 2.64E-08 2.47E-08 2.78E-08 2.48E-08 1.25E-08 8.59E-09 6.29E-09 5.69E-09 5.48E-09 6.87E-09

30 1.16E-08 1.59E-08 1.10E-08 1.64E-08 1.08E-08 1.19E-08 1.62E-08 1.14E-08 1.68E-08 1.43E-08 1.44E-08 1.09E-08 1.02E-08 1.02E-08 1.26E-08

31 1.38E-08 1.38E-08 1.48E-08 1.39E-08 1.41E-08 1.42E-08 1.42E-08 1.52E-08 1.42E-08 9.64E-09 7.76E-09 5.86E-09 5.45E-09 5.40E-09 6.56E-09

32 2.01E-08 9.57E-09 1.56E-08 8.49E-09 2.26E-08 2.05E-08 9.84E-09 1.59E-08 8.73E-09 1.62E-08 8.56E-09 5.86E-09 4.88E-09 3.84E-09 4.11E-09

33 1.45E-08 7.60E-09 2.04E-08 6.84E-09 2.23E-08 1.48E-08 7.84E-09 2.07E-08 7.06E-09 9.03E-09 5.66E-09 3.99E-09 3.28E-09 2.64E-09 2.80E-09

34 1.97E-08 1.33E-08 3.29E-08 1.30E-08 2.52E-08 2.01E-08 1.37E-08 3.34E-08 1.33E-08 8.70E-09 6.23E-09 4.72E-09 4.09E-09 3.63E-09 4.22E-09

35 3.03E-08 9.06E-08 2.10E-08 1.91E-07 2.24E-08 3.07E-08 9.10E-08 2.13E-08 1.92E-07 1.50E-08 9.94E-09 7.33E-09 6.30E-09 5.64E-09 6.52E-09

36 1.49E-08 8.18E-09 2.29E-08 7.39E-09 2.64E-08 1.52E-08 8.42E-09 2.33E-08 7.61E-09 1.06E-08 6.48E-09 4.54E-09 3.74E-09 2.97E-09 3.15E-09

37 3.12E-08 7.41E-08 2.18E-08 1.25E-07 2.39E-08 3.15E-08 7.46E-08 2.22E-08 1.25E-07 1.44E-08 9.58E-09 7.07E-09 6.10E-09 5.30E-09 6.02E-09

38 1.17E-07 1.80E-08 3.03E-08 1.44E-08 5.74E-08 1.18E-07 1.84E-08 3.07E-08 1.47E-08 1.53E-08 1.07E-08 7.17E-09 5.86E-09 4.65E-09 4.92E-09
Document No. ORAUT-TKBS-0006-4 Revision No. 02 Effective Date:

06/05/2007 Page 52 of 45

ATTACHMENT A

Page 14 of 18

Node Standard Deviations 

1 2 3 4 5 6 7 8 9 10 11 12 13 14 15

1 4.56E-08 2.40E-09 4.81E-09 1.78E-09 8.48E-09 4.58E-08 2.50E-09 4.86E-09 1.83E-09 2.38E-09 1.40E-09 7.50E-10 6.57E-10 5.90E-10 5.83E-10

2 2.53E-09 3.04E-08 1.40E-09 6.99E-09 1.59E-09 2.60E-09 3.03E-08 1.38E-09 7.04E-09 3.88E-09 1.71E-09 8.27E-10 7.12E-10 5.67E-10 6.93E-10

3 1.03E-08 2.01E-09 3.79E-08 1.43E-09 2.40E-08 1.04E-08 2.03E-09 3.78E-08 1.45E-09 1.81E-09 1.21E-09 5.54E-10 4.96E-10 4.11E-10 4.17E-10

4 2.61E-09 1.73E-08 1.57E-09 2.76E-08 2.52E-09 2.62E-09 1.75E-08 1.58E-09 2.77E-08 3.85E-09 1.96E-09 8.56E-10 6.50E-10 5.98E-10 7.07E-10

5 1.67E-08 2.12E-09 9.23E-09 1.56E-09 3.77E-08 1.68E-08 2.14E-09 9.25E-09 1.59E-09 1.97E-09 1.12E-09 6.48E-10 5.15E-10 4.59E-10 4.81E-10

6 1.31E-09 1.43E-09 9.47E-10 1.08E-09 1.07E-09 1.31E-09 1.46E-09 9.49E-10 1.08E-09 4.64E-08 2.21E-09 1.01E-09 9.46E-10 7.16E-10 8.42E-10

7 1.23E-09 1.37E-09 1.37E-09 1.91E-09 1.43E-09 1.28E-09 1.40E-09 1.39E-09 1.96E-09 3.31E-09 1.35E-07 3.38E-09 1.93E-09 1.77E-09 1.48E-09

8 2.27E-09 2.19E-09 1.88E-09 2.09E-09 2.04E-09 2.31E-09 2.24E-09 1.93E-09 2.17E-09 2.51E-09 2.15E-09 9.19E-08 5.89E-09 3.01E-09 2.72E-09

9 1.79E-09 1.74E-09 1.51E-09 1.53E-09 1.63E-09 1.82E-09 1.79E-09 1.54E-09 1.60E-09 2.10E-09 2.07E-09 5.64E-09 4.56E-08 4.10E-09 2.75E-09

10 1.39E-09 1.46E-09 1.21E-09 1.39E-09 1.28E-09 1.41E-09 1.48E-09 1.21E-09 1.40E-09 1.72E-09 2.59E-09 2.99E-09 3.84E-09 3.64E-08 2.27E-09

11 1.88E-09 2.34E-09 1.64E-09 2.09E-09 1.73E-09 1.92E-09 2.35E-09 1.64E-09 2.13E-09 2.88E-09 5.04E-09 4.18E-09 4.10E-09 2.48E-09 5.83E-08

12 2.13E-09 9.54E-10 1.32E-09 1.31E-09 2.31E-09 2.15E-09 9.68E-10 1.34E-09 1.32E-09 8.05E-09 1.98E-09 1.20E-09 9.00E-10 7.73E-10 7.34E-10

13 7.38E-10 6.61E-10 6.07E-10 5.91E-10 5.47E-10 7.73E-10 6.88E-10 6.33E-10 6.13E-10 1.71E-09 1.03E-09 6.01E-10 4.91E-10 4.01E-10 4.44E-10

14 1.21E-09 1.50E-09 9.81E-10 1.48E-09 1.08E-09 1.22E-09 1.55E-09 1.02E-09 1.53E-09 1.66E-09 2.16E-09 3.41E-09 3.62E-09 2.60E-09 2.25E-09

15 8.95E-10 9.56E-10 8.20E-10 8.91E-10 8.75E-10 9.04E-10 9.71E-10 8.33E-10 9.03E-10 1.41E-09 1.77E-09 2.67E-09 2.55E-09 4.18E-09 1.41E-09

16 1.18E-09 1.32E-09 9.77E-10 1.22E-09 1.03E-09 1.19E-09 1.34E-09 9.86E-10 1.24E-09 2.19E-09 3.24E-09 1.95E-09 2.70E-09 2.52E-09 1.90E-09

17 6.55E-10 4.19E-10 8.49E-10 4.48E-10 8.52E-10 6.85E-10 4.35E-10 8.61E-10 4.60E-10 1.17E-09 5.76E-10 3.99E-10 3.65E-10 2.58E-10 3.00E-10

18 1.71E-09 1.30E-09 1.85E-09 1.22E-09 1.71E-09 1.77E-09 1.34E-09 1.91E-09 1.26E-09 1.29E-09 8.61E-10 5.56E-10 5.28E-10 4.99E-10 4.80E-10

19 9.43E-10 2.35E-09 1.19E-09 2.70E-09 1.20E-09 9.53E-10 2.37E-09 1.26E-09 2.75E-09 2.19E-09 1.97E-09 8.45E-10 7.50E-10 6.49E-10 7.60E-10

20 7.57E-09 5.60E-09 3.17E-09 2.30E-09 3.64E-09 7.63E-09 5.67E-09 3.22E-09 2.37E-09 1.96E-09 1.38E-09 6.71E-10 6.05E-10 5.87E-10 5.74E-10

21 2.44E-09 3.20E-09 1.89E-09 2.83E-09 1.95E-09 2.50E-09 3.23E-09 1.94E-09 2.87E-09 3.51E-09 1.27E-08 2.82E-09 1.91E-09 1.72E-09 1.65E-09

22 1.37E-08 3.53E-09 2.90E-09 2.26E-09 4.54E-09 1.37E-08 3.62E-09 2.88E-09 2.31E-09 2.30E-09 1.30E-09 7.43E-10 6.98E-10 5.86E-10 6.39E-10

23 9.69E-10 8.85E-10 1.50E-09 8.68E-10 1.08E-09 9.85E-10 9.39E-10 1.56E-09 9.09E-10 9.14E-10 5.88E-10 4.47E-10 4.21E-10 4.13E-10 4.38E-10

24 8.76E-10 1.08E-09 9.15E-10 1.05E-09 7.95E-10 9.12E-10 1.15E-09 9.36E-10 1.10E-09 9.87E-10 1.33E-09 7.23E-10 5.78E-10 5.67E-10 7.50E-10

25 6.87E-10 9.11E-10 6.56E-10 8.74E-10 5.50E-10 7.12E-10 9.48E-10 6.74E-10 9.07E-10 9.14E-10 1.41E-09 7.94E-10 6.15E-10 6.13E-10 9.00E-10

26 1.06E-09 1.35E-09 1.11E-09 1.33E-09 1.03E-09 1.10E-09 1.41E-09 1.17E-09 1.40E-09 1.22E-09 1.23E-09 5.87E-10 4.75E-10 4.72E-10 5.87E-10

27 3.42E-10 2.50E-10 5.62E-10 2.47E-10 4.83E-10 3.63E-10 2.66E-10 5.83E-10 2.74E-10 2.93E-10 2.46E-10 2.15E-10 2.01E-10 1.94E-10 1.78E-10

28 1.22E-09 1.35E-09 1.03E-09 1.36E-09 1.18E-09 1.24E-09 1.38E-09 1.06E-09 1.35E-09 1.87E-09 3.06E-09 1.34E-09 1.06E-09 8.62E-10 2.33E-09

29 2.60E-09 3.94E-09 2.25E-09 4.08E-09 1.92E-09 2.67E-09 4.02E-09 2.28E-09 4.14E-09 2.61E-09 1.60E-09 7.93E-10 6.77E-10 5.40E-10 6.33E-10

30 8.33E-10 1.38E-09 7.45E-10 1.25E-09 8.16E-10 8.53E-10 1.37E-09 7.55E-10 1.25E-09 7.26E-10 1.80E-09 1.05E-09 8.55E-10 7.09E-10 7.90E-10

31 1.38E-09 1.62E-09 1.00E-09 1.67E-09 8.93E-10 1.44E-09 1.66E-09 1.05E-09 1.71E-09 1.63E-09 1.26E-09 6.38E-10 6.36E-10 5.60E-10 5.70E-10

32 1.86E-09 5.11E-10 2.09E-09 4.04E-10 2.96E-09 1.88E-09 5.45E-10 2.11E-09 4.09E-10 1.71E-09 9.12E-10 6.30E-10 5.49E-10 3.87E-10 4.75E-10

33 2.10E-09 1.03E-09 2.74E-09 8.49E-10 2.95E-09 2.18E-09 1.06E-09 2.81E-09 8.78E-10 8.41E-10 7.49E-10 4.33E-10 3.38E-10 3.00E-10 3.09E-10

34 1.96E-09 1.03E-09 3.56E-09 1.14E-09 2.45E-09 2.06E-09 1.11E-09 3.70E-09 1.22E-09 1.11E-09 7.46E-10 4.72E-10 3.60E-10 3.25E-10 3.46E-10

35 4.55E-09 7.64E-09 1.32E-09 1.85E-08 2.09E-09 4.55E-09 7.56E-09 1.34E-09 1.85E-08 2.91E-09 1.53E-09 6.83E-10 5.49E-10 5.62E-10 6.28E-10

36 2.19E-09 8.72E-10 2.47E-09 8.44E-10 4.32E-09 2.25E-09 9.11E-10 2.57E-09 8.79E-10 1.21E-09 8.34E-10 5.18E-10 4.17E-10 3.46E-10 3.63E-10

37 3.76E-09 9.30E-09 2.01E-09 1.75E-08 2.88E-09 3.77E-09 9.39E-09 2.02E-09 1.77E-08 3.11E-09 1.28E-09 6.13E-10 6.04E-10 5.23E-10 5.70E-10

38 4.56E-08 2.40E-09 4.81E-09 1.78E-09 8.48E-09 4.58E-08 2.50E-09 4.86E-09 1.83E-09 2.38E-09 1.40E-09 7.50E-10 6.57E-10 5.90E-10 5.83E-10
Document No. ORAUT-TKBS-0006-4 Revision No. 02 Effective Date: 06/05/2007 Page 53 of 56

ATTACHMENT A

Page 15 of 18

Table A-11. Ar-41 submersion gamma dose (Sv) and skin dose (Sv).

Ar-41 Gamma dose GSD Skin dose GSD

1944 1.15E-06 1.71 1.90E-06 1.71

1945 5.28E-06 1.34 8.67E-06 1.34

1946 3.77E-06 1.37 6.19E-06 1.37

1947 3.70E-06 1.38 6.08E-06 1.38

1948 3.84E-06 1.36 6.31E-06 1.36

1949 5.38E-06 1.33 8.84E-06 1.33

1950 6.92E-06 1.41 1.14E-05 1.41

1951 7.45E-06 1.38 1.22E-05 1.38

1952 8.40E-06 1.34 1.38E-05 1.34

1953 2.20E-05 1.28 3.61E-05 1.28

1954 2.20E-05 1.28 3.61E-05 1.28

1955 2.65E-05 1.47 4.35E-05 1.47

1956 3.27E-05 1.46 5.37E-05 1.46

1957 3.27E-05 1.46 5.37E-05 1.46

1958 3.28E-05 1.46 5.38E-05 1.46

1959 3.28E-05 1.46 5.38E-05 1.46

1960 3.28E-05 1.46 5.38E-05 1.46

1961 3.28E-05 1.46 5.38E-05 1.46

1962 3.28E-05 1.46 5.38E-05 1.46

1963 3.28E-05 1.46 5.38E-05 1.46

1964 3.47E-05 1.44 5.69E-05 1.44

1965 3.38E-05 1.45 5.56E-05 1.45

1966 3.35E-05 1.45 5.51E-05 1.45

1967 3.34E-05 1.45 5.48E-05 1.45

1968 3.29E-05 1.46 5.40E-05 1.46

1969 3.18E-05 1.48 5.23E-05 1.48

1970 1.80E-05 1.51 2.95E-05 1.51

1971 1.13E-05 1.61 1.86E-05 1.61

1972 8.62E-06 1.61 1.42E-05 1.61

1973 8.62E-06 1.61 1.42E-05 1.61

1974 4.31E-06 1.61 7.08E-06 1.61

1975 2.66E-06 1.61 4.37E-06 1.61

1976 3.05E-06 1.61 5.01E-06 1.61

1977 1.13E-05 1.61 1.85E-05 1.61

1978 9.48E-06 1.61 1.56E-05 1.61

1979 7.41E-06 1.61 1.22E-05 1.61

1980 1.98E-06 1.61 3.26E-06 1.61

1981 5.60E-06 1.61 9.20E-06 1.61

1982 9.83E-06 1.61 1.61E-05 1.61

1983 1.04E-05 1.61 1.71E-05 1.61

1984 6.64E-06 1.61 1.09E-05 1.61

1985 5.95E-06 1.61 9.77E-06 1.61

1986 1.03E-05 1.61 1.70E-05 1.61

1987 3.88E-07 1.61 6.37E-07 1.61

1989 through 2001 all values are 0.00 Reactors Shut Down
Document No. ORAUT-TKBS-0006-4 Revision No. 02 Effective Date: 06/05/2007 Page 54 of 56

ATTACHMENT A

Page 16 of 18

Table A-12. Intakes of particulate radionuclides (Bq/yr).

Date

Ce/Pr-144 Cs/Ba-137 Pu-239 Ru/Rh-103

Intake GSD Intake GSD Intake GSD Intake GSD

1944 1.45E-01 2.46 4.18E-03 2.46 9.75E-06 12.00 1.83E-01 2.87

1945 3.79E+01 1.59 1.28E+00 1.59 6.84E-03 7.04 3.40E+01 1.68

1946 6.64E+01 1.56 2.35E+00 1.56 1.47E-02 6.43 4.28E+01 1.64

1947 4.05E+01 1.55 1.48E+00 1.55 9.71E-03 6.30 2.13E+01 1.62

1948 1.32E+01 1.69 5.20E-01 1.69 2.11E-03 8.18 4.30E+00 1.85

1949 3.42E-01 1.55 1.32E-02 1.55 2.21E-04 6.16 1.08E-01 1.62

1950 6.20E-01 1.55 2.61E-02 1.55 3.50E-04 6.10 2.22E-01 1.63

1951 9.56E-01 1.54 3.57E-02 1.55 5.16E-04 6.02 6.12E-01 1.61

1952 3.53E+00 1.54 1.37E-01 1.54 1.62E-03 5.69 2.60E+01 2.01

1953 1.20E+01 1.86 2.21E-01 1.54 2.37E-03 5.82 2.47E+02 2.59

1954 7.05E+00 1.54 2.68E-01 1.54 2.81E-03 5.79 5.84E+02 2.65

1955 7.34E+00 1.54 3.08E-01 1.55 3.37E-03 5.87 1.96E+01 1.66

1956 6.85E+00 1.54 2.56E-01 1.55 3.73E-03 5.71 1.65E+01 1.65

1957 1.24E+01 1.51 4.42E-01 1.51 5.40E-03 5.56 2.35E+01 1.64

1958 1.49E+01 1.53 5.00E-01 1.53 4.81E-03 5.78 2.30E+01 1.68

1959 1.80E+01 1.52 6.18E-01 1.52 4.67E-03 5.85 9.65E+00 1.61

1960 2.06E+01 1.53 7.18E-01 1.53 4.65E-03 6.06 1.04E+01 1.63

1961 2.04E+01 1.53 7.07E-01 1.53 6.06E-03 5.84 9.55E+00 1.59

1962 6.36E+01 1.53 2.67E-01 1.53 2.90E-03 7.70 3.88E+00 1.65

1963 5.66E+01 1.56 2.45E-01 1.55 2.47E-03 6.19 3.24E+00 1.67

1964 6.35E+01 1.55 2.54E-01 1.55 3.12E-03 6.19 4.07E+00 1.67

1965 5.94E+01 1.54 2.64E-01 1.54 4.53E-03 7.67 3.13E+00 1.64

1966 4.05E+01 1.58 1.84E-01 1.59 3.71E-03 6.91 1.91E+00 1.81

1967 5.25E+01 1.54 2.10E-01 1.54 5.45E-05 6.58 1.79E+00 1.70

1968 5.05E+01 1.54 1.81E-01 1.54 4.95E-05 6.60 9.22E-01 1.69

1969 3.57E+01 1.53 1.32E-01 1.54 3.78E-05 6.66 3.44E-01 1.68

1970 7.87E+00 1.76 2.85E-02 1.77 8.20E-06 8.05 7.37E-02 2.32

1971 1.44E+01 1.64 1.32E-01 1.62 1.80E-05 7.74 4.15E-02 2.37

1972 1.47E+00 2.06 2.22E-02 2.03 1.17E-06 10.50 1.78E-03 2.39

All years from 1973 through 1982 have values of 0.00

1983 1.47E-02 1.42 3.13E-04 1.42

1984 5.05E-02 1.42 2.02E-02 1.42 3.74E-03 1.42 2.53E-04 1.42

1985 5.05E-02 1.42 5.05E-03 1.42 5.05E-03 1.42 2.63E-01 1.42

1986 4.40E-03 1.42 1.52E-03 1.42 1.01E-02 1.42

1987 2.02E-05 1.42 2.02E-04 1.42 1.01E-04 1.42

1988 5.05E-05 1.42 4.04E-04 1.42 1.01E-04 1.42 2.53E-04 1.42

1989 6.57E-04 1.42 4.92E-04 1.43

1990 3.49E-04 1.42 1.80E-04 1.43

1991 2.07E-03 1.42 2.64E-04 1.43

1992 1.16E-02 1.42 2.82E-04 1.43

1993 9.09E-03 1.42 3.36E-04 1.43

1994 3.33E-04 1.42 2.52E-04 1.43

1995 3.28E-04 1.42 7.20E-05 1.43

1996 3.03E-04 1.42 1.44E-04 1.43

1997 4.85E-04 1.42 7.20E-05 1.43

1998 1.11E-04 1.42 1.20E-04 1.43

1999 4.29E-05 1.42 1.26E-04 1.43

2000 9.09E-05 1.42 3.06E-04 1.43

2001 7.58E-05 1.42 9.00E-05 1.43
Document No. ORAUT-TKBS-0006-4 Revision No. 02 Effective Date: 06/05/2007 Page 55 of 56

ATTACHMENT A

Page 17 of 18

Date

Ru/Rh-106 Sr/Y-90 Zr/Nb-95 I-131

Intake GSD Intake GSD Intake GSD Intake GSD

1944 1.19E-02 2.87 4.84E-03 2.46 1.91E-01 5.33 2.88E+02 3.78

1945 4.09E+00 1.69 1.45E+00 1.59 5.24E+01 2.60 1.04E+05 1.94

1946 7.28E+00 1.63 2.67E+00 1.56 7.92E+01 2.41 2.42E+04 1.90

1947 4.48E+00 1.61 1.68E+00 1.55 5.16E+01 2.33 6.30E+03 2.02

1948 1.44E+00 1.85 5.93E-01 1.69 3.08E+01 2.50 3.48E+02 1.90

1949 4.30E-02 1.62 1.50E-02 1.55 2.36E+00 3.50 1.24E+03 3.50

1950 8.50E-02 1.62 2.97E-02 1.55 1.95E-02 4.62 1.14E+03 2.23

1951 1.35E-01 1.61 4.05E-02 1.54 5.74E-01 2.32 5.66E+03 2.11

1952 1.01E+01 1.92 1.57E-01 1.54 1.46E+00 2.47 2.27E+03 1.96

1953 9.22E+01 2.51 2.51E-01 1.54 2.11E+00 2.53 1.17E+03 1.94

1954 1.93E+02 2.47 3.06E-01 1.54 2.05E+00 2.39 4.14E+02 1.89

1955 7.38E+00 1.68 3.51E-01 1.55 2.64E+00 2.51 4.33E+02 2.29

1956 6.29E+00 1.69 2.89E-01 1.55 2.14E+00 2.48 7.69E+01 2.16

1957 7.64E+00 1.62 5.03E-01 1.51 3.12E+00 2.43 1.70E+02 2.19

1958 5.76E+00 1.66 5.72E-01 1.53 4.16E+00 2.49 4.31E+02 2.09

1959 4.14E+00 1.62 6.99E-01 1.52 3.79E+00 2.49 1.37E+02 1.91

1960 3.49E+00 1.65 8.17E-01 1.53 4.00E+00 2.56 1.23E+02 2.21

1961 5.91E+00 1.62 8.04E-01 1.52 3.72E+00 2.48 5.14E+01 1.91

1962 2.26E+00 1.62 1.08E+00 1.53 2.61E+00 2.57 4.03E+01 2.56

1963 2.03E+00 1.67 9.66E-01 1.56 2.29E+00 2.63 5.15E+01 2.75

1964 2.26E+00 1.65 1.07E+00 1.55 2.47E+00 2.68 3.84E+01 1.99

1965 2.06E+00 1.64 1.03E+00 1.54 2.26E+00 2.58 3.22E+01 2.28

1966 1.51E+00 1.84 7.95E-01 1.65 5.82E-01 3.44 2.32E+01 2.25

1967 2.08E+00 1.63 1.04E+00 1.54 1.08E+00 2.84 1.65E+01 2.16

1968 2.28E+00 1.63 1.07E+00 1.53 7.45E-01 2.70 3.07E+00 2.24

1969 1.73E+00 1.62 8.54E-01 1.54 3.49E-01 2.66 7.54E-01 2.61

1970 3.79E-01 1.97 1.91E-01 1.76 5.46E-02 4.13 2.80E-01 2.13

1971 5.18E-01 1.79 5.19E-01 1.64 6.04E-02 4.17 1.26E-01 1.89

1972 4.25E-02 2.42 4.46E-02 2.07 7.54E-03 4.48 2.56E-01 1.40

All years from 1973 through 1982 have values of 0.00

1983 1.52E-03 1.42

1984 1.01E-01 1.42 1.16E-02 1.42

1985 3.03E-01 1.42 4.29E-03 1.42 1.02E-01 1.42

1986 2.02E-01 1.42 1.06E-04 1.42 1.02E-01 1.42

1987 1.01E-02 1.42 1.01E-04 1.42 1.02E-04 1.42

1988 9.09E-02 1.42 5.05E-05 1.42 2.03E-04 1.42

1989 1.11E-02 1.42 2.32E-03 1.42 8.63E-03 1.42

1990 1.41E-03 1.42 2.68E-03 1.42 7.11E-04 1.42

1991 1.47E-03 1.42 1.21E-03 1.42

1992 2.22E-04 1.42

1993 2.02E-06 1.42 1.87E-04 1.42

1994 1.01E-04 1.42

1995 9.09E-06 1.42 1.26E-04 1.42

1996 2.27E-04 1.42

1997 2.98E-04 1.42

1998 1.87E-04 1.42

1999 2.12E-04 1.42

2000 1.67E-04 1.42

2001 1.47E-04 1.42
Document No. ORAUT-TKBS-0006-4 Revision No. 02 Effective Date: 06/05/2007 Page 56 of 56

ATTACHMENT A

Page 18 of 18

Table A-13. Intakes from 3

H from 

108-B (Bq/yr). 

Tritium

GM Intake GSD

1949 6.39E+02 1.68

1950 5.74E+03 1.68

1951 2.53E+04 1.68

1952 3.72E+04 1.68

1953 3.66E+03 1.68

1954 1.15E+05 1.68